FINAL SAFETY ANALYSIS REPORT CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF THE PLANT

FINAL SAFETY ANALYSIS REPORT
CHAPTER 1
INTRODUCTION AND GENERAL DESCRIPTION
OF THE PLANT
CCNPP Unit 3
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FSAR: Chapter 1.0
1.0
Introduction And General Description of the Plant
INTRODUCTION AND GENERAL DESCRIPTION OF THE PLANT
This chapter of the U.S. EPR Final Safety Analysis Report (FSAR) is incorporated by reference
with supplements as identified in the following sections.
CCNPP Unit 3
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FSAR: Chapter 1.0
1.1
Introduction
INTRODUCTION
This section of the U.S. EPR FSAR is incorporated by reference with the following supplements.
This Final Safety Analysis Report is submitted to the Nuclear Regulatory Commission as part of
an application for a Class 103 combined license (COL) to construct and operate a nuclear
power facility under the provisions of 10 CFR 52, Subpart C. {This FSAR is also being submitted
to the Nuclear Regulatory Commission to support the necessary Materials Licenses requested
in the COL Application Letter (UNE, 2008) to receive, possess and use byproduct, source and
special nuclear material under 10 CFR 30, 10 CFR 40 and 10 CFR 70, respectively.}This nuclear
power facility is designated {Calvert Cliffs Nuclear Power Plant (CCNPP) Unit 3.}This FSAR
incorporates the FSAR prepared for the design certification application for the AREVA
evolutionary pressurized water reactor, (herein referred to as the U.S. EPR). AREVA NP, the
entity sponsoring the design certification application for the U.S. EPR, submitted a revised U.S.
EPR design certification application to the NRC on August 31, 2010 (AREVA, 2010).
Upon approval and issuance of the design certification for the U.S. EPR, the approved version
of the FSAR for the U.S. EPR and the associated Appendix to 10 CFR 52 documenting the
design certification for the U.S. EPR are incorporated by reference into this COL application.
Within each section, or subsection, only supplemental information or departures from the
certified design are presented. If the U.S. EPR provides sufficient information, this FSAR will
state ”This section of the U.S. EPR FSAR is incorporated by reference” at the section (i.e. X.Y)
level and ”No departures or supplements” at the highest subsection level where such a
statement can be made. Likewise, if a section contains additional information, a statement is
provided at the section level to identify if departures or supplements are provided. Section
and subsection numbering is only provided to the extent necessary to provide sufficient
context to correlate the information provided in this FSAR with the information provided in
the U.S. EPR FSAR.
Supplemental information is provided in three forms. Additional information, such as this text,
is provided in the appropriate section. The second form is COL Item responses. COL Items are
statements in the U.S. EPR FSAR that indicate that the COL applicant must provide additional
information. Each applicable COL Item is restated in the equivalent section/subsection in this
FSAR and information to address the COL Item is provided. The final type of supplemental
information provided in this FSAR is to address conceptual design information provided in the
U.S. EPR FSAR. Conceptual design information is presented in the U.S. EPR FSAR enclosed in
double brackets ”[[ ]]”. As stated in the U.S. EPR FSAR, the conceptual design information is
outside the scope of the U.S. EPR standard design, and is not submitted for certification as part
of that document. Like COL Items, the conceptual design information is restated in this FSAR
followed by the site specific information.
Departures from the U.S. EPR FSAR are identified in the applicable sections of the COL
Application.
{U.S. EPR nuclear power plants that are licensed, constructed, and operated in cooperation
with UniStar Nuclear Operating Services LLC (UniStar Nuclear Operating Services) are
standardized to the extent practical. This allows for a standardized FSAR. Information that is
unique to {CCNPP Unit 3} is enclosed in braces ”{ }”. Information not enclosed in braces is
generic for all UniStar Nuclear Operating Services facilities. Minor changes are made within the
generic text that are not identified as site specific. These includes figure and table numbers,
which are organized sequentially within sections, and minor grammatical changes necessary
to support introduction of site specific text.}
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FSAR: Chapter 1.0
Introduction
The U.S. EPR FSAR includes the following COL Item in Section 1.1:
A combined license (COL) applicant that references the U.S. EPR design
certification and proposes a multiunit license application will provide the changes
and additional information needed to license a multiunit plant.
This COL Item is addressed as follows:
{This COL application is for a single unit U.S. EPR. As such, no changes or additional
information are needed to address this COL Item.}
1.1.1
Plant Location
The U.S. EPR FSAR includes the following COL Item in Section 1.1.1:
A COL applicant that references the U.S. EPR design certification will identify the
specific plant site location.
This COL Item is addressed as follows:
{CCNPP Unit 3 is colocated with two currently licensed reactors (CCNPP Units 1 and 2). CCNPP
Unit 3 is located south of the existing nuclear power plant on the existing CCNPP site. The
CCNPP site consists of 2070 acres (838 hectares) in Calvert County, Maryland, on the west bank
of Chesapeake Bay, approximately halfway between the mouth of the bay and its headwaters
at the Susquehanna River. As reflected in Figure 2.1-1, CCNPP Unit 3 is within the CCNPP Units
1 and 2 Exclusion Area Boundary and the CCNPP Units 1 and 2 Independent Spent Fuel
Storage Installation Exclusion Area Boundary. The site is approximately 40 mi (64 km)
southeast of Washington D.C. and 7.5 mi (12 km) north of Solomons Island, Maryland.
Figure 1.1-1 through Figure 1.1-3 illustrate the location of the site, and the arrangement of the
three units.
CCNPP Unit 3 shares the following structures, systems, and components with CCNPP Units 1
and 2:
ᅁ Offsite transmission system
ᅁ Chesapeake Bay intake channel and embayment
ᅁ Meteorological tower
ᅁ Emergency Operations Facility (EOF)
ᅁ Barge dock
In accordance with 10 CFR 52.79(a)(31) (CFR, 2008), the following provides an assessment of
the potential hazards to the structures, systems, and components (SSCs) important to safety of
operating units resulting from construction activities at a multiunit site and identifies that
managerial and administrative controls are to be used to provide assurance that the limiting
conditions for operation (LCOs) at the operating units, are not exceeded as a result of new
plant construction activities.
The managerial and administrative controls include coordination, with CCNPP Units 1 and 2, of
construction activities which have the potential for causing CCNPP Units 1 and 2 to exceed
LCOs or have an adverse impact on the availability of safety and risk significant SSCs. CCNPP
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FSAR: Chapter 1.0
Introduction
Units 1 and 2 procedures and processes are currently in place to control activities that could
affect compliance with an LCO or availability of safety and risk significant SSCs, e.g.,
equipment clearance and tagout procedures, access controls, and switchyard controls.
The potential hazards associated with CCNPP Unit 3 construction activities include, but are not
limited to general construction activities such as site exploration, grading, clearing, and
installation of drainage and erosioncontrol measures; boring, drilling, dredging, pile driving
and excavating; transportation, storage and warehousing of equipment; construction,
erection, and fabrication of new facilities; and connection, integration, and testing. Specific
potential impacts to CCNPP Units 1 and 2 SSCs include the following:
ᅁ Relocation and construction of transmission lines/towers
ᅁ Construction of Sheetpile wall and Intake Pipes on the shore of the Chesapeake Bay
next to the embayment for the intake structures for CCNPP Units 1 and 2
ᅁ Meteorological data transmission modifications (electrical and instrumentation tieins
and connections to provide input to CCNPP Unit 3 facilities)
ᅁ Modification to the existing Emergency Operations Facility to accommodate CCNPP
Unit 3 Emergency Planning activities
The majority of the CCNPP Units 1 and 2 SSCs important to safety are contained and protected
within safetyrelated structures. Managerial controls will protect these internal SSCs from
postulated construction hazards by maintaining the integrity and design basis of the
safetyrelated structures and foundations. Heavy load drop controls, crane boom failure
standoff requirements, ground vibration controls and construction generated missiles controls
are examples of managerial controls that shall be established to provide this reasonable
assurance.
Other managerial controls shall be established to ensure that hazardous materials and gasses
are controlled, cooling water supplies are protected, instrumentation is protected from
vibrations, and the SSCs are protected from site excavation issues. These managerial controls
prevent or mitigate external construction impacts that could affect these SSCs. These controls
also prevent or mitigate unnecessary challenges to CCNPP Units 1 and 2 safety systems that
could be caused by potential CCNPP Unit 3 construction activity hazards, such as disruption of
offsite transmission lines or impact to cooling water supplies. Onsite construction activities
with potential safety significance to the operating units shall also be addressed in accordance
with established CCNPP Unit 1 and 2 procedures and processes, as described above.
Construction impacts on security controls are addressed in the CCNPP Unit 3 Security Plan.
The CCNPP Unit 3 Security Plan is provided in Part 8 of the COL application.}
Additional site details are provided in Chapter 2.
1.1.2
Containment Type
No departures or supplements.
1.1.3
Reactor Type
No departures or supplements.
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1.1.4
Introduction
Power Output
No departures or supplements.
1.1.5
Schedule
The U.S. EPR FSAR includes the following COL Item in Section 1.1.5:
A COL applicant that references the U.S. EPR design certification will provide the
estimated schedules for completion of construction and commercial operation.
This COL Item is addressed as follows:
{The following major activities are scheduled*:
Order Ultra Heavy Forgings for Reactor Vessel and NSSS Components
Submit Environmental Report for CCNPP Unit 3
Submit Certificate of Public Convenience and Necessity (CPCN) Application to the
State of Maryland
Submit Design Certification Application for the U.S. EPR
Submit Remainder of COL Application for CCNPP Unit 3
State of Maryland Issues CPCN for CCNPP Unit 3
NRC Issues Design Certification for U.S. EPR
NRC Issues COL
Plant Construction Starts
Construction Complete
Plant Startup Testing Begins
Commercial Operation
* dates are provided as representative projections
1.1.6
April 2006
(complete)
July 2007
(complete)
November 2007
(complete)
December 2007
(complete)
March 2008
(complete)
December 2008
October 2010
March 2011
April 2011
July 2015
July 2015
December 2015}
Format and Content
1.1.6.1
Regulatory Guide 1.206
This FSAR follows the U.S. EPR FSAR organization and numbering. The U.S. EPR FSAR was
written in accordance with the format and content of Regulatory Guide 1.206, (NRC, 2007).
This FSAR provides departures and supplemental information from the standard U.S. EPR
design that is unique to the {CCNPP Unit 3} project. If the information provided in the U.S. EPR
FSAR sufficiently addresses the Regulatory Guide 1.206 content for {CCNPP Unit 3}, this FSAR
will state ”No departures or supplements” at the highest section level where such a statement
can be made.
In addition, this FSAR may add a final section or subsection (when necessary) for references
made within this document. References will be provided if they are used in this FSAR even if
they were identified within the U.S. EPR FSAR.
1.1.6.2
Standard Review Plan
No departures or supplements.
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1.1.6.3
Introduction
Text, Tables and Figures
Tables and figures are identified by the section or subsection in which they appear and are
numbered sequentially. For example, Table 1.1-1 and Figure 1.1-1 would be the first table and
figure appearing in Section 1.1. Figures consist of diagrams, plots, pictures, graphs or other
illustrations. Tables and figures are located at the end of the applicable section (X.Y)
immediately following the text.
1.1.6.4
Numbering of Pages
Pages are numbered sequentially within each chapter.
1.1.6.5
Proprietary Information
This document contains no proprietary information.
1.1.6.6
Acronyms
Table 1.1-1 provides a list of acronyms that are used in this document.
1.1.6.7
COL Information Items
The COL Items in the U.S. EPR FSAR are discussed in Section 1.8.
1.1.6.8
Tense
This section is added as a supplement to the U.S. EPR FSAR.
This FSAR is a licensing basis document that will control plant design and operations after the
COL is issued and is generally written in the present tense. Plant design and configuration are
described in the present tense although the plant is not yet built. Similarly, programs,
procedures, and organizational matters are generally described in the present tense although
such descriptions may not yet be implemented. Accordingly, the use of the present tense in
this FSAR should be understood as describing the plant, programs and procedures, and
organization as they will exist when in place, and not as a representation that they are already
in place.
1.1.7
References
{This section is added as a supplement to the U.S. EPR FSAR.
AREVA, 2010. Submittal of Revision 2 of the U.S. EPR Final Safety Analysis Report for Design
Certification, S. Sloan letter to U. S. Nuclear Regulatory Commission Document Desk, dated
August 31, 2010.
CFR, 2008. Title 10, Code of Federal Regulations, Part 52.79, Contents of Applications;
Technical Information in Final Safety Analysis Report, U.S. Nuclear Regulatory Commission,
2008.
NRC, 2007. Combined License Applications for Nuclear Power Plants (LWR Edition),
Regulatory Guide 1.206, Revision 0, U.S. Nuclear Regulatory Commission, March 2007.
UNE, 2008. UniStar Nuclear Energy Letter, G. Gibson to U.S. Nuclear Regulatory Commission,
UN#08003, Submittal of Revision 2 to the Partial Combined License Application for the Calvert
Cliffs Nuclear Power Plant, Unit 3, dated March 14, 2008.}
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Table 1.1-1— {Acronyms Used in this Document}
(Page 1 of 6)
Acronym
Description
χ/Q
Atmospheric Dispersion Value
A/E
Architect – Engineer
AASHTO
American Association of State Highway and Transportation Officials
AB
Access Building
ACI
American Concrete Institute
AFDD
Accumulated Freezing DegreeDays
ALOHA
Areal Locations of Hazardous Atmospheres
ANS
American Nuclear Society
ANSI
American National Standards Institute
ANSS
Advanced National Seismic Network
AOV
AirOperated Valve
AQCR
Air Quality Control Region
ASCE
American Society of Civil Engineers
ASHRAE
American Society of Heating, Refrigerating, and Air Conditioning Engineers
AWWA
American Water Works Association
BE
Best Estimate
BF
Butterfly Valve
BGE
Baltimore Gas and Electric
BMA
Brunswick Magnetic Anomaly
BWI
Baltimore/Washington International
C/NM
Consumable/NonMetallic
CAM
Continuous Air Monitor
CBBT
Chesapeake Bay Bridge Tunnel
CBIS
Common Basemat Intake Structures
CCNPP
Calvert Cliffs Nuclear Power Plant
CD
Certified Design
CEUS
Central and Eastern United States
CLSZ
CharlevoixLa Malbaie Seismic Zone
CK
Check Valve
CPCN
Certificate of Public Convenience and Necessity
CPT
Cone Penetrometer Test
CR
Control Room
CRE
Control Room Envelope
CRR
Cyclic Resistance Ratio
CSDRS
Certified Seismic Design Response Spectra
CSR
Cyclic Stress Ratio
CTI
Cooling Tower Institute
CVSZ
Central Virginia Seismic Zone
D.C.
District of Columbia
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Table 1.1-1— {Acronyms Used in this Document}
(Page 2 of 6)
Acronym
Description
D/Q
Deposition Factor
DAC
Derived Air Concentration
DC
Direct Current
DCPLNG
Dominion Cove Point Liquefied Natural Gas
DI
Diaphragm Valve
DNAG
Decade of North American Geology
DOE
Department of Energy
DOT
Department of Transportation
EC
Erosion/Corrosion
ECFS
East Coast Fault System
ECL
Effluent Concentration Limits
ECMA
East Coast Magnetic Anomaly
EMC
Electromagnetic Compatibility
EPA
Environmental Protection Agency
EPIX
Equipment Performance and Information Exchange
EPR
Evolutionary Power Reactor
EQ
Environmental Qualification
ER
Environmental Report or Electrical Resistivity
ERC
Estuarine Research Center
ES
Engineered Safeguards
ESP
Early Site Permit
EST
Earth Science Team
ESWB
Essential Service Water Building
ETR
Energy Transfer Ratio
FERC
Federal Energy Regulatory Commission
FFD
Fitness for Duty
FHA
Fire Hazards Analysis
FIRS
Foundation Input Response Spectra
FOS
Factor of Safety
FPE
Fire Protection Engineer
GB
Globe Valve
GMRS
Ground Motion Response Spectra
GSA
Geological Society of America
GT
Gate Valve
HF
High Frequency
HMR
Hydrometeorological Report
HO
Hydraulic Operated
HPS
Health Physics Society
ICEA
Insulated Cable Engineers Association
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Table 1.1-1— {Acronyms Used in this Document}
(Page 3 of 6)
Acronym
Description
ICRP
International Commission on Radiological Protection
ID
Identification
IDLH
Immediately Dangerous to Life and Health
IRC
Independent Review Committee
ISFSI
Independent Spent Fuel Storage Installation
JFD
Joint Frequency Distribution
JPM
Job Performance Measures
KKS
Kraftworks Kennzeichen System
LB
Lower Bound
LERF
Large Early Release Frequency
LF
Low Frequency
LFL
Lower Flammability Limit
LiDAR
Light Detection and Ranging
LLC
Limited Liability Company
LNG
Liquefied Natural Gas
LPS
Layer Parallel Shortening
LSS
Low Safety Significance
LSZ
Lancaster Seismic Zone
MA
Manual Actuated
MD
Maryland
MDE
Maryland Department of Environment
MDNR
Maryland Department of Natural Resources
MED
Master Equipment Database
MMBO
Million Barrels of Oil
MEDEVAC
Medical Evacuation
MEOW
Maximum Envelopes of Water
MGS
Maryland Geological Survey
MHHW
Mean Higher High Water
MLLW
Mean Lower LowWater
MLW
Mean Low Water
MMI
Modified Mercalli Intensity
MOM
Maximum of the MEOWS
MPSSZ
Middleton PlaceSummerville Seismic Zone
MRFF
Maintenance Rule Functional Failure
MSL
Mean Sea Level
MSS
Medium Safety Significance
NAAQS
National Ambient Air Quality Standards
NAS
Naval Air Station
NEC
National Electrical Code
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Table 1.1-1— {Acronyms Used in this Document}
(Page 4 of 6)
Acronym
Description
NEI
Nuclear Energy Institute
NERC
North American Electric Reliability Corporation
NGVD 29
National Geodetic Vertical Datum of 1929
NHC
National Hurricane Center
NIC
National Ice Center
NIOSH
National Institute for Occupational Safety and Health
NJ
New Jersey
NLSWE
Nonlinear Shallow Water Equations
NOAA
National Oceanic and Atmospheric Administration
NP
NonProprietary
NPDES
National Pollution Discharge Elimination System
NPRDS
Nuclear Plant Reliability Data System
NRC
Nuclear Regulatory Commission
NRCS
U.S. National Resources Conservation Service
NWS
National Weather Service
NYAL
New York – Alabama Lineament
OBE
Operating Basis Earthquake
OCR
Over Consolidation Ratio
ODCM
Offsite Dose Calculation Manual
OJT
OntheJob Training
OSHA
Occupational Safety and Health Administration
P
Proprietary
PA
Pilot Actuated
PCP
Process Control Program
PEPCO
Potomac Electric Power Company
PGA
Peak Ground Acceleration
PJM
Pennsylvania, New Jersey, and Maryland
Regional Transmission Organization
PL
Plug Valve
PMH
Probable Maximum Hurricane
PMSS
Probable Maximum Storm Surge
PMT
Probable Maximum Tsunami
PMWP
Probable Maximum Winter Precipitation
PPRP
Power Plant Research Program
PSAR
Preliminary Safety Analysis Report
PSHA
Probabilistic Seismic Hazard Analysis
PSP
Physical Security Plan
PST
PreService Testing
PTS
Pressurized Thermal Shock
QAPD
Quality Assurance Program Description
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Table 1.1-1— {Acronyms Used in this Document}
(Page 5 of 6)
Acronym
Description
QC
Quality Control
RCA
Radiologically Controlled Area
RCTS
Resonant Column Torsional Shear
RD
Rupture Disk Valve
REMP
Radiological Environmental Monitoring Program
RETS
Radiological Effluent Technical Specifications
RMS
Records Management System
RSZ
Ramapo Seismic Zone
RV
Relief Valve
RVT
Random Vibration Theory
SA
Self Actuated
SAR
Safety Analysis Report
SARA
Superfund Amendments and Reauthorization Act
SCDOT
South Carolina Department of Transportation
SCR
Stable Continental Region
SDWIS
Safe Drinking Water Information System
SECPOP
Sector Population Land Fraction, and Economic Estimation Program
SEUSSN
Southeastern U.S. Seismic Network
SGA
Salisbury Geophysical Anomaly
SLOSH
Sea, Lake, and Overland Surges from Hurricanes
SOV
SolenoidOperated Valve
SPH
Standard Project Hurricane
SPT
Standard Penetration Test
SSE
Safe Shutdown Earthquake
SSI
SoilStructure Interaction
SSSI
StructureSoilSturcture Interaction
STEL
ShortTerm Exposure Limit
TEDE
Total Effective Dose Equivalent
TIP
Trial Implementation Project
TLD
Thermoluminescent Dosimeter
TNT
Trinitrotoluene
TOC
Top of Concrete
TRT
Test Review Team
TSU
Tsunami Model
TWA
Time Weighted Average
UB
Upper Bound
UCSS
Updated Charleston Seismic Source
UFL
Upper Flammability Limit
UFSAR
Updated Final Safety Analysis Report
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Table 1.1-1— {Acronyms Used in this Document}
(Page 6 of 6)
Acronym
Description
UHS
Uniform Hazard Spectra or Ultimate Heat Sink
UHS MWIS
Ultimate Heat Sink Makeup Water Intake Structure
USACE
U.S. Army Corps of Engineers
USCG
United States Coast Guard
USCS
Unified Sort Classification System
USGS
U.S. Geological Survey
USNSN
U.S. National Seismograph Network
VA
Virginia
Vp
Compressional Wave Velocity
Vs
ShearWave Velocity
WOH
Weight of Hammer
WOR
Weight of Rod
WUS
Western United States
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Introduction
Figure 1.1-1— {50 mi (80 km) Surrounding Area}
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Introduction
Figure 1.1-2— {10 mi (16 km) Surrounding Area}
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Introduction
Figure 1.1-3— {Site Area Map}
FSAR: Chapter 1.0
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1.2
General Plant Description
GENERAL PLANT DESCRIPTION
This section of the U.S. EPR FSAR is incorporated by reference with the following supplements.
The U.S. EPR FSAR includes the following COL Item in Section 1.2:
A COL applicant that references the U.S. EPR design certification will identify those
sitespecific features of the plant likely to be of special interest because of their
relationship to safety. The COL applicant will also highlight items such as unusual
site characteristics, solutions to particularly difficult engineering, construction
problems, and significant extrapolations in technology represented by the site
specific design.
This COL Item is addressed as follows:
{There are no sitespecific features of the plant considered to be of special interest because of
their relationship to safety. There are no unusual site characteristics, and no particularly
difficult engineering or construction problems, and no significant extrapolations in
technology represented by the site specific design.}
1.2.1
Principal Design Criteria, Operating Characteristics, and Safety Considerations
No departures or supplements.
1.2.2
Site Description
The U.S. EPR FSAR includes the following conceptual design information in Section 1.2.2 for
the Turbine Building:
Turbine Building – [[ Figures 1.228 through 1.248. ]]
The above conceptual design information is addressed as follows:
An Alstom turbine generator design has been selected. This is the reference design reflected
in U.S. EPR FSAR Section 10.1, 10.2, and 10.4.7. Figures in Section 1.2 of the U.S. EPR FSAR are
incorporated by reference.
The U.S. EPR FSAR includes the following conceptual design information in Section 1.2.2 for
the Access Building:
Access Building – [[ Figures 1.250 through 1.258. ]]
The above conceptual design information is addressed as follows:
The reference Access Building shown in U.S. EPR FSAR Figures 1.250 through 1.258 is
incorporated by reference.
The U.S. EPR FSAR includes the following COL Item in Section 1.2.2:
A COL applicant that references the U.S. EPR design certification will provide a
sitespecific layout figure.
This COL Item is addressed as follows:
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General Plant Description
{The site specific layout is presented in Figure 1.1-3 showing the CCNPP Unit 3 circulating
water system cooling tower and intake structures on the Chesapeake Bay. An enlargement of
the layout of the Nuclear and Turbine Building Islands is presented in Figure 1.2-1.}
The U.S. EPR FSAR includes the following COL Item in Section 1.2.2:
A COL applicant that references the U.S. EPR design certification will provide
sitespecific general arrangement drawings for the Turbine Building and Access
Building.
This COL Item is addressed as follows:
The reference plant Turbine Building and Access Building are utilized. The general
arrangement drawings provided in the U.S. EPR FSAR are incorporated by reference as
discussed above.
1.2.3
Plant Description
1.2.3.1
1.2.3.1.1
Introduction to the U.S. EPR Design and Building Arrangement
Overview
No departures or supplements.
1.2.3.1.2
Buildings and Arrangement
The U.S. EPR FSAR includes the following conceptual design information in Section 1.2.3.1.2 for
the Turbine Building:
Physical separation also protects the [[Turbine Building and Switchgear Building.
The Turbine Building houses the components of the steam condensate main
feedwater cycle, including the turbinegenerator. This building is located in a
radial position with respect to the Reactor Building, but is independent from the
NI. The Turbine Building is further described in Section 3.7.2. The Switchgear
Building, which contains the power supply, the instrumentation and controls (I&C)
for the balance of plant, and the SBO diesel generators, is located next to the
Turbine Building and is physically separate from the NI. The Switchgear Building is
shown in Figure 1.21.]]
The above conceptual design information is addressed as follows:
The reference Turbine Building and Switchgear Building designs are utilized. The information
as stated in the U.S. EPR FSAR is incorporated by reference.
1.2.3.2
Reactor Coolant System
No departures or supplements.
1.2.3.3
Engineered Safety Features and Emergency Systems
No departures or supplements.
1.2.3.4
Instrumentation and Control Systems
No departures or supplements.
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1.2.3.5
1.2.3.5.1
General Plant Description
Electrical Systems
General
The U.S. EPR FSAR includes the following conceptual design information in Section 1.2.3.5.1:
[[ For operational flexibility and reliability, the switchyard is configured in either a
breakerandahalf or double breaker scheme. ]]
The above conceptual design information is addressed as follows:
{The CCNPP Unit 3 switchyard is configured in a breaker and a half arrangement.}
1.2.3.5.2
Offsite Power
No departures or supplements.
1.2.3.5.3
Onsite Power System
No departures or supplements.
1.2.3.6
Power Conversion Systems
No departures or supplements.
1.2.3.7
Fuel Handling and Storage Systems
No departures or supplements.
1.2.3.8
Cooling Water and Other Auxiliary Systems
No departures or supplements.
1.2.3.9
Radioactive Waste Management Systems
No departures or supplements.
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General Plant Description
Figure 1.2-1— {CCNPP Unit 3 Nuclear and Turbine Building Island Layout}
FSAR: Chapter 1.0
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FSAR: Chapter 1.0
1.3
Comparisons with Similar Facility Designs
COMPARISONS WITH SIMILAR FACILITY DESIGNS
This section of the U.S. EPR FSAR is incorporated by reference.
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FSAR: Chapter 1.0
1.4
Identification of Agents and Contractors
IDENTIFICATION OF AGENTS AND CONTRACTORS
This section of the U.S. EPR FSAR is incorporated by reference with the following supplements.
1.4.1
Applicant – Program Manager
{Calvert Cliffs 3 Nuclear Project, LLC and UniStar Nuclear Operating Services, LLC are applying
for a combined license for CCNPP Unit 3. The owner of the proposed project is Calvert Cliffs 3
Nuclear Project, LLC. The operator of the proposed project is UniStar Nuclear Operating
Services, LLC. The contact with the NRC during the licensing process is UniStar Nuclear Energy,
LLC. UniStar Nuclear Energy, LLC is discussed in Section 1.4.2.
Sections 1.4.1.1 and 1.4.1.2 are added as supplements to the U.S. EPR FSAR.
1.4.1.1
Calvert Cliffs 3 Nuclear Project, LLC
Calvert Cliffs 3 Nuclear Project, LLC is a limited liability company and is an indirect subsidiary
(through UniStar Nuclear Holdings, LLC and UniStar Project Holdings, LLC, which operate as
holding companies) of UniStar Nuclear Energy, LLC. UniStar Nuclear Energy is owned jointly by
Constellation New Nuclear, LLC and by EDF, Inc. Constellation New Nuclear is a member
(through Constellation Nuclear, LLC) of Constellation Energy Group, Inc. EDF Development is
an indirect subsidiary of (through EDF International, SA) of Èlecticitè de Franco, SA.
The principal offices of Calvert Cliffs 3 Nuclear Project, LLC are located in Baltimore, Maryland.
Calvert Cliffs 3 Nuclear Project, LLC is organized under the laws of the State of Delaware
pursuant to the Limited Liability Company Agreement of Calvert Cliffs 3 Nuclear Project, LLC
dated March 10, 2008, by UniStar Project Holdings, LLC. Calvert Cliffs 3 Nuclear Project, LLC will
be one of the licensees and will own CCNPP Unit 3.
Constellation Energy Group is a holding company for several companies involved with electric
and gas energy. Constellation Energy Group, through its subsidiaries, is a major generator of
electric power and a leading supplier of competitive electricity, with a power generation
portfolio of over 8,700 megawatts. The output of Constellation Energy Group’s plants is sold
by Constellation Energy Group’s commodities business, Constellation Energy Commodities
Group, Inc., to many of the nation’s leading distribution utilities, energy companies, and
cooperatives.
1.4.1.2
UniStar Nuclear Operating Services, LLC
UniStar Nuclear Operating Services, LLC has been formed to be a licensee and to operate U.S.
EPR nuclear power plants in the United States. The principal offices of UniStar Nuclear
Operating Services, LLC are located in Baltimore, Maryland.
UniStar Nuclear Operating Services, LLC is organized under the laws of the State of Delaware
pursuant to the entity’s articles of incorporation, dated May 12, 2006. This entity will be one of
the licensees for, and will provide the operating services for, CCNPP Unit 3.}
1.4.2
Other Contractors and Participants
The U.S. EPR FSAR includes the following COL Item in Section 1.4.2:
A COL applicant that references the U.S. EPR design certification will identify the
prime agents or contractors for the construction and operation of the nuclear
power plant.
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FSAR: Chapter 1.0
Identification of Agents and Contractors
This COL Item is addressed as follows:
Design responsibility for the U.S. EPR nuclear power plant resides with AREVA NP Inc. (AREVA
NP) for the portions of the facility included in the design certification application. AREVA NP
has headquarters in Lynchburg, Virginia, and major design organizations in Lynchburg,
Virginia; Charlotte, North Carolina; and Marlborough, Massachusetts. AREVA NP is an AREVA
and Siemens company. AREVA NP and its predecessor companies have designed light water
reactors for over 40 years. As such, AREVA NP has extensive nuclear design experience in
addition to maintaining fabrication facilities for fuel and major components in Europe and the
United States. AREVA NP will provide additional services during conduct of startup testing.
{Bechtel North American Power Corporation (Bechtel) provides design services for portions of
the facility design not included in the U.S. EPR design certification (balance of plant) and is
expected to be the prime contractor for the construction of CCNPP Unit 3. Bechtel has
extensive architecturalengineering experience, and has participated in the design and
construction of more than 150 nuclear power plants worldwide. Bechtel provides design
assistance to AREVA NP which retains design responsibility for the U.S. EPR.
UniStar Nuclear Energy, LLC. provides project management, engineering, procurement,
training, regulatory affairs and startup, testing, and commissioning support during the design,
construction, startup and operation of CCNPP Unit 3.
CCNPP Unit 3 will be operated by UniStar Nuclear Operating Services, LLC as discussed in
Section 1.4.1.2.}
Other various agents and contractors provide specialized services to the project.
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FSAR: Chapter 1.0
1.5
Requirements for Further Technical Information
REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION
This section of the U.S. EPR FSAR is incorporated by reference.
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FSAR: Chapter 1.0
1.6
Material Referenced
MATERIAL REFERENCED
This section of the U.S. EPR FSAR is incorporated by reference with the following supplements.
The U.S. EPR FSAR includes the following COL Item in Section 1.6:
A COL applicant that references the U.S. EPR design certification will include any
sitespecific topical reports that are incorporated by reference as part of the COL
application in Table 1.6-1.
This COL Item is addressed as follows:
Table 1.6-1 of this FSAR contains a list of topical reports submitted to the NRC to support this
application.
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FSAR: Chapter 1.0
Material Referenced
Table 1.6-1— {Reports Referenced}
Report No.
Title/Revision
Date Submitted
to the NRC
FSAR Section
NEI 0708A
Generic FSAR Template Guidance for Ensuring that Occupational
Radiation Exposures Are As Low As Is Reasonably Achievable
(ALARA), Revision 0
October 2009
12.1.3
NEI 0703A
Generic FSAR Template Guidance for Radiation Protection
Program Description, Revision 0
May 2009
12.1.3
12.5
NEI 0613A
Template for an Industry Training Program Description, Revision 2 March 2009
13.2
UNTR06001A
Quality Assurance Program Description, Revision 0
April 2007
17.5
NEI 0702A
Generic FSAR Template Guidance for Maintenance Rule Program
Description for Plants Licensed Under 10 CFR Part 52, Revision 0
March 2008
17.7
NEI 0606
Fitness for Duty Program Guidance for New Revision Power Plant
Construction Sites, Revision 5
August 2009
13.7
NEI 0407
Pressurized Water Reactor Sump Performance Evaluation
Methodology
December 2004
6.3.2.2.2
NEI 0002
Probabilistic Risk Assessment (PRA) Peer Review Process
Guidance, Revision 1
May 2006
19.1.2
NEI 0709A
Generic FSAR Template Guidance for Offsite Dose Calculation
Manual (ODCM) Description, Revision 0
March 2009
11.5
NEI 0710A
Generic FSAR Template Guidance for Process Control Program
(PCP), Revision 0
August 2009
11.4
NEI 0808A
Generic FSAR Template Guidance for Life Cycle Minimization of
Contamination
October 2009
11.2,11.3,11.4,11.5
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FSAR: Chapter 1.0
1.7
Drawings and Other Detailed Information
DRAWINGS AND OTHER DETAILED INFORMATION
This section of the U.S. EPR FSAR is incorporated by reference with the following supplements.
1.7.1
Electrical and Instrumentation and Control Drawings
The U.S. EPR FSAR includes the following COL Item in Section 1.7.1:
A COL applicant that references the U.S. EPR design certification will list additional
site specific instrumentation and control functional diagrams and electrical
oneline diagrams included in the COL FSAR in Table 1.7-1 and supplement the
figure legends, if applicable.
This COL Item is addressed as follows:
Table 1.7-1 contains a list of site specific instrumentation and control functional diagrams and
electrical oneline diagrams included in the COL FSAR.
1.7.2
Piping and Instrumentation Diagrams
The U.S. EPR FSAR includes the following COL Item in Section 1.7.2:
A COL applicant that references the U.S. EPR design certification will list additional
site specific P&IDs included in the COL FSAR in Table 1.7-2 and supplement the
figure legend, if applicable.
This COL Item is addressed as follows:
A list of site specific P&IDs included in the {CCNPP Unit 3} FSAR is presented in Table 1.72.
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FSAR: Chapter 1.0
Drawings and Other Detailed Information
Table 1.7-1— {I&C Functional and Electrical One Line Diagrams}
FSAR Figure Number
Title
Figure 8.2-2
CCNPP Unit 3 500 kv Switchyard Single Line Diagram
Figure 8.3-1
CCNPP Unit 3 Emergency Power Supply System Single Line Drawing (three sheets)
Figure 8.3-2
CCNPP Unit 3 Normal Power Supply System Single Line Drawing (five sheets)
Figure 8.3-3
CCNPP Unit 3 Transformer 30BBT03 Distribution System Single Line Drawing
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FSAR: Chapter 1.0
Drawings and Other Detailed Information
Table 1.7-2— {Piping and Instrumentation Diagrams}
FSAR Figure Number
Title
Figure 9.2-1
Potable Water System
Figure 9.2-2
Sanitary Waste Water System
Figure 9.2-3
Normal Makeup, Ultimate Heat Sink Makeup, Blowdown & Chemical Treatment
Figure 9.2-7
Raw Water & Desalinated Water Supply
Figure 9.4-1
Turbine Building Ventilation System
Figure 9.4-2
UHS Makeup Water Intake Structure Ventilation System
Figure 9.5-1
CCNPP Unit 3 Fire Water Distribution System Cooling Tower Loop
Figure 9.5-2
CCNPP Unit 3 Fire Water Distribution System Intake Structure Loop
Figure 9.5-3
CCNPP Unit 3 UHS Makeup Water Intake Structure
Figure 10.4-1
Circulating Water System P& ID (Circulating Water Pump Building)
Figure 10.4-2
Circulating Water System P& ID (Turbine Building)
Figure 10.4-3
Circulating Water System Makeup System P& ID
Figure 10.4-6
Circulating Water System Blowdown Flowpath
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FSAR: Chapter 1.0
1.8
Interfaces with Standard Designs and Early Site Permits
INTERFACES WITH STANDARD DESIGNS AND EARLY SITE PERMITS
This section of the U.S. EPR FSAR is incorporated by reference with the following supplements.
The U.S. EPR FSAR includes the following COL Item in Section 1.8:
A COL applicant that references the U.S. EPR design certification will describe
where the interface requirements are satisfied in the COL Final Safety Analysis
Report (FSAR) to demonstrate compatibility with the U.S. EPR design.
This COL Item is addressed as follows:
Interface requirements for systems, structures, and components (SSCs) that relate to specific
mechanical, electrical, nuclear, or structural systems are identified in appropriate sections of
the FSAR. Table 1.8-1 provides a crossreference to the description of these interfaces.
1.8.1
COL Information Items
The U.S. EPR FSAR includes the following COL Item in Section 1.8.1:
A COL applicant that references the U. S. EPR design certification will identify the
FSAR section, or provide a list, that demonstrates how the COL information items
have been addressed.
This COL Item is addressed as follows:
The text of the COL Items and COL No. identifier listed in Table 1.82 of the U.S. EPR FSAR are
presented in Table 1.8-2. For each COL Item listed, the corresponding section of this FSAR that
addresses the COL Item is identified. Additional explanatory comments are provided as
necessary or appropriate.
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FSAR: Chapter 1.0
1.8.2
Interfaces with Standard Designs and Early Site Permits
Departures
The U.S. EPR FSAR includes the following COL Item in Section 1.8.2:
A COL applicant that references the U. S. EPR design certification will provide a list
of any departures from the FSAR in the COL FSAR.
This COL Item is addressed as follows:
{The list of departures from the U.S. EPR FSAR is as follows:
Maximum Differential Settlement (across the basemat)
Maximum Annual Average Atmospheric Dispersion Factor (0.5 mile
limiting sector)
Accident Atmospheric Dispersion Factor from (0 2 hour, Low
Population Zone, 1.5 miles)
InStructure Response Spectra
Toxic Gas Detection and Isolation
Minimum Shear Wave Velocity
Maximum NonCoincident Wet Bulb Temperature Value at 0%
Exceedance (85°F)
Coefficient of Static Friction
Generic Technical Specifications and Bases Setpoint Control
Program
FSAR 2.5.4 and 3.8.5
FSAR 2.3.5
FSAR 2.3.4 and 15.0.3
FSAR 3.7.2.5.2
FSAR 3.11, 6.4, 9.4.1 and 14.2.12
FSAR 2.5.4.2.5.8 and COLA Part 10, ITAAC
Table 2.41
FSAR 2.0, 2.3, and 9.2.1
FSAR 3.8.5.5
FSAR 16 (COLA Part 4)
Justification for these departures is presented in Part 7 of the COL application.}
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FSAR: Chapter 1.0
Interfaces with Standard Designs and Early Site Permits
Table 1.8-1— FSAR Sections that Demonstrate Conformance to U.S. EPR FSAR Interface
Requirements
Item
No.
Interface
Interface Type
FSAR Section
11
Switchgear Building
U.S. EPR Interface
1.2, 8.3, 8.4
12
Access Building
U.S. EPR Interface
1.2, 3.7.2
13
Turbine Building
U.S. EPR Interface
1.2, 3.7.2
14
Fire Protection Storage Tanks and Building
U.S. EPR Interface
1.2, 3.7.2
21
Envelope of U.S. EPR site related design
Site Parameter
2.0, Table 2.0-1
22
Consequences of potential hazards from nearby industrial, transportation
and military facilities
Site Parameter
2.2
23
Sitespecific χ/Q values based on sitespecific meteorological data at the
exclusion area boundary (EAB), low population zone (LPZ), and control room
Site Parameter
2.3
24
Sitespecific seismic characteristics
Site Parameter
2.5, 3.7
25
Soil conditions and profiles
Site Parameter
2.5
26
Bearing pressure of soil beneath the nuclear island basemat
Site Parameter
2.5
27
Foundation settlements
Site Parameter
2.5
31
Missiles generated from nearby facilities
Site Parameter
3.5
32
Missiles generated by tornadoes or extreme winds
Site Parameter
3.5
33
Aircraft hazards
Site Parameter
3.5
34
Sitespecific loads that lie within the standard plant design envelope for
Seismic Category I structures
Site Parameter
3.8
35
Buried conduit and duct banks, and pipe and pipe ducts
U.S. EPR Interface
3.8
81
Offsite AC power transmission system connections to the switchyard and
the connection to the plant power distribution system
U.S. EPR Interface
8.2
82
Onsite AC power transmission system connections to the switchyard and
the connection to the plant power distribution system
U.S. EPR Interface
8.3
83
Auxiliary power and generator transformer areas
U.S. EPR Interface
8.2
84
Lightning protection and grounding system grid
U.S. EPR Interface
8.3.1
92
Provide support systems such as makeup water, blowdown and chemical
treatment (to control biofouling) for the UHS
U.S. EPR Interface
9.2.5
93
Raw water system
U.S. EPR Interface
9.2.9
94
Fire water distribution system
U.S. EPR Interface
9.5.1
101
Design details for circulating water system including makeup water, and
water treatment
U.S. EPR Interface
10.4.5
111
Process Control program and program aspects of process and effluent
monitoring and sampling
U.S. EPR Interface
11.5
131
Sitespecific information for administrative, operating, emergency,
maintenance, and other operating procedures.
U.S. EPR Interface
13.5
132
Sitespecific emergency plan
U.S. EPR Interface
13.3
133
Sitespecific security assessment and Physical Security Plan
U.S. EPR Interface
13.6
141
Sitespecific information for development of the initial test program
U.S. EPR Interface
14.2
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Table 1.8-2— FSAR Sections that Address COL Items
(Page 1 of 20)
Item No.
Description
Section
1.11
A COL applicant that references the U.S. EPR design certification and proposes a multiunit license
application will provide the changes and additional information needed to license a multiunit plant.
1.12
A COL applicant that references the U.S. EPR design certification will identify the specific plant site
location.
1.1.1
1.13
A COL applicant that references the U.S. EPR design certification will provide the estimated schedules
for completion of construction and commercial operation.
1.1.5
1.21
A COL applicant that references the U.S. EPR design certification will identify those site specific features
of the plant likely to be of special interest because of their relationship to safety. The COL applicant will
also highlight items such as unusual site characteristics, solutions to particularly difficult engineering,
construction problems, and significant extrapolations in technology represented by the site specific
design.
1.22
A COL applicant that references the U.S. EPR design certification will provide a sitespecific layout
figure.
1.2.2
1.23
A COL applicant that references the U.S. EPR design certification will provide sitespecific general
arrangement drawings for the Turbine Building and Access Building.
1.2.2
1.41
A COL applicant that references the U.S. EPR design certification will identify the prime agents or
contractors for the construction and operation of the nuclear power plant.
1.4.2
1.61
A COL applicant that references the U.S. EPR design certification will include any sitespecific topical
reports that are incorporated by reference as part of the COL application in Table 1.6-1.
1.71
A COL applicant that references the U.S. EPR design certification will list additional site specific
instrumentation and control functional diagrams and electrical oneline diagrams included in the COL
FSAR in Table 1.7-1 and supplement the figure legends, if applicable.
1.7.1
1.72
A COL applicant that references the U.S. EPR design certification will list additional site specific P&IDs
included in the COL FSAR in Table 1.7-2 and supplement the figure legend, if applicable.
1.7.2
1.81
A COL applicant that references the U.S. EPR design certification will describe where the interface
requirements are satisfied in the COL FSAR to demonstrate compatibility with the U.S. EPR design.
1.8
1.82
A COL applicant that references the U. S. EPR design certification will identify the FSAR section, or
provide a list, that demonstrates how the COL information items have been addressed.
1.8.1
1.83
A COL applicant that references the U. S. EPR design certification will provide a list of any departures
from the FSAR in the COL FSAR.
1.8.2
1.91
A COL applicant that references the U.S. EPR design certification will review and address the
conformance with Regulatory Criteria in effect six months before the docket date of the COL
application for the sitespecific portions and operational aspects of the facility design.
1.9
2.01
A COL applicant that references the U.S. EPR design certification will compare the characteristics of its
proposed site to the site parameters in Table 2.11. If the characteristics of the site fall within the
assumed site parameters in Table 2.11, then the U.S. EPR standard design is bounding for the site. For
sitespecific characteristics that are outside the bounds of the assumptions presented in Table 2.11, the
COL applicant will demonstrate that the U.S. EPR design acceptably meets the regulatory requirements,
given the more limiting sitespecific characteristic. In such an instance, the COL applicant will also
demonstrate that the design commitments and acceptance criteria described in the FSAR do not need
to be changed, or will propose new design commitments or acceptance criteria, or both.
2.0
2.11
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
related to site location and description, exclusion area authority and control, and population
distribution.
2.1
2.21
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
related to the identification of potential hazards stemming from nearby industrial, transportation, and
military facilities within the site vicinity, including an evaluation of potential accidents (such as
explosions, toxic chemicals, and fires).
2.2
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1.2
1.6
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FSAR: Chapter 1.0
Interfaces with Standard Designs and Early Site Permits
Table 1.8-2— FSAR Sections that Address COL Items
(Page 2 of 20)
Item No.
Description
Section
2.22
A COL applicant that references the U.S. EPR design certification will provide information concerning
sitespecific evaluations to determine the consequences that potential accidents at nearby industrial,
transportation, and military facilities could have on the site. The information provided by the COL
applicant will include specific changes made to the U.S. EPR design to qualify the design of the site
against potential external accidents with an unacceptable probability of severe consequences.
2.2.3
2.31
If A COL applicant that references the U.S. EPR design certification identifies sitespecific meteorology
values outside the range of the site parameters in Table 2.11, then the COL applicant will demonstrate
the acceptability of the sitespecific values in the appropriate sections of the Combined License
application.
2.3
2.32
A COL applicant that references the U.S. EPR design certification will provide sitespecific characteristics
for regional climatology.
2.3.1
2.33
A COL applicant that references the U.S. EPR design certification will provide sitespecific characteristics
for local meteorology.
2.3.2
2.34
A COL applicant that references the U.S. EPR design certification will provide the sitespecific, onsite
meteorological measurement program.
2.3.3
2.35
A COL applicant that references the U.S. EPR design certification will provide a description of the
atmospheric dispersion modeling used in evaluating potential design basis events to calculate
concentrations of hazardous materials (e.g., flammable or toxic clouds) outside building structures
resulting from the onsite and/or offsite airborne releases of such materials.
2.3.4
2.36
A COL applicant that references the U.S. EPR design certification will confirm that site specific χ/Q
values, based on sitespecific meteorological data, are bounded by those specified in Table 2.11 at the
EAB, LPZ and at the control room. For sitespecific χ/Q values that exceed the bounding χ/Q values, a
COL applicant that references the U.S. EPR design certification will demonstrate that the radiological
consequences associated with the controlling design basis accident continue to meet the dose
reference values given in 10 CFR 50.34 and the control room operator dose limits given in GDC 19
using sitespecific χ/Q values.
2.37
A COL applicant that references the U.S. EPR design will provide χ/Q values for each cumulative
frequency distribution which exceeds the median value (50 percent of the time) as part of the
assessment of the postulated impact of an accident on the environment.
2.38
A COL applicant that references the U.S. EPR design certification will provide the sitespecific,
longterm diffusion estimates for routine releases. In developing this information, the COL applicant
should consider the guidance provided in RG 1.23, RG 1.109, RG 1.111, and RG 1.112.
2.3.5
2.39
A COL applicant that references the U.S EPR design certification will also provide estimates of annual
average atmospheric dispersion (χ/Q values) and deposition (D/Q values) for 16 radial sectors to a
distance of 50 miles (80 km) from the plant as part of its environmental assessment.
2.3.5
2.310
A COL applicant that references the U.S. EPR design certification will describe the means for providing
UHS makeup sufficient to meet the maximum evaporative and drift water loss after 72 hours through
the remainder of the 30 day period consistent with RG 1.27.
2.3.1.2
2.41
A COL applicant that references the U.S. EPR design certification will provide a sitespecific description
of the hydrologic characteristics of the plant site.
2.4.1
2.42
A COL applicant that references the U.S. EPR design certification will identify sitespecific information
related to flood history, flood design considerations, and effects of local intense precipitation.
2.4.2
2.43
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
to describe the probable maximum flood of streams and rivers and the effect of flooding on the design.
2.4.3
2.44
A COL applicant that references the U.S. EPR design certification will verify that the site specific
potential hazards to the safetyrelated facilities due to the failure of upstream and downstream water
control structures are within the hydrogeologic design basis.
2.4.4
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2.3.4.2
2.3.4.2.2
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FSAR: Chapter 1.0
Interfaces with Standard Designs and Early Site Permits
Table 1.8-2— FSAR Sections that Address COL Items
(Page 3 of 20)
Item No.
Description
Section
2.45
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
on the probable maximum surge and seiche flooding and determine the extent to which safetyrelated
plant systems require protection. The applicant will also verify that the sitespecific characteristic
envelope is within the design maximum flood level, including consideration of wind effects.
2.4.5
2.46
A COL applicant that references the U.S. EPR design will provide sitespecific information and
determine the extent to which safetyrelated facilities require protection from tsunami effects,
including Probable Maximum Tsunami Flooding.
2.4.6
2.47
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
regarding ice effects and design criteria for protecting safetyrelated facilities from iceproduced
effects and forces with respect to adjacent water bodies.
2.4.7
2.48
A COL applicant that references the U.S. EPR design certification will evaluate the potential for freezing
temperatures that may affect the performance of the ultimate heat sink makeup, including the
potential for frazil and anchor ice, maximum ice thickness, and maximum cumulative degreedays
below freezing.
2.4.7
2.49
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
and describe the design basis for cooling water canals and reservoirs used for makeup to the UHS
cooling tower basins.
2.4.8
2.410
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
and demonstrate that in the event of diversion or rerouting of the source of cooling water, alternate
water supplies will be available to safetyrelated equipment.
2.4.9
2.411
A COL applicant that references the U.S. EPR design certification will use sitespecific information to
compare the location and elevations of safetyrelated facilities, and of structures and components
required for protection of safetyrelated facilities, with the estimated static and dynamic effects of the
design basis flood conditions.
2.4.10
2.412
A COL applicant that references the U.S. EPR design certification will identify natural events that may
reduce or limit the available cooling water supply, and will verify that an adequate water supply exists
for operation or shutdown of the plant in normal operation, anticipated operational occurrences, and
in low water conditions.
2.4.11
2.413
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
to identify local and regional groundwater reservoirs, subsurface pathways, onsite use, monitoring or
safeguard measures, and to establish the effects of groundwater on plant structures.
2.4.12
2.414
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
on the ability of the groundwater and surface water environment to delay, disperse, dilute, or
concentrate accidental radioactive liquid effluent releases, regarding the effects that such releases
might have on existing and known future uses of groundwater and surface water resources.
2.4.13
2.415
A COL applicant that references the U.S. EPR design certification will describe any emergency measures
required to implement flood protection in safetyrelated facilities and to verify there is an adequate
water supply for shutdown purposes.
2.4.14
2.51
A COL applicant that references the U.S. EPR design certification will use sitespecific information to
investigate and provide data concerning geological, seismic, geophysical, and geotechnical
information.
2.5.1
2.52
A COL applicant that references the U.S. EPR design certification will review and investigate
sitespecific details of seismic, geophysical, geological, and geotechnical information to determine the
safe shutdown earthquake (SSE) ground motion for the site and compare site specific ground motion
to the Certified Seismic Design Response Spectra (CSDRS) for the U.S. EPR.
2.5.2
2.53
A COL applicant that references the U.S. EPR design certification will compare the final sitespecific soil
characteristics with the U.S. EPR design generic soil parameters and verify that the sitespecific seismic
characteristics are enveloped by the CSDRS (anchored at 0.3 g PGA) and the 10 generic soil profiles
discussed in Section 2.5.2, 2.5.4.7 and 3.7.1 and summarized in Table 3.7.16.
2.5.2.6
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Table 1.8-2— FSAR Sections that Address COL Items
(Page 4 of 20)
Item No.
Description
Section
2.54
A COL applicant that references the U.S. EPR design certification will verify that sitespecific foundation
soils beneath the foundation basemats of Seismic Category I structures have the capacity to support
the bearing pressure with a factor of safety of 3.0 under static conditions.
2.5.4.10.1
2.55
A COL applicant that references the U.S. EPR design certification will investigate sitespecific surface
and subsurface geologic, seismic, geophysical, and geotechnical aspects within 25 miles around the
site and evaluate any impact to the design. The COL applicant will demonstrate that no capable faults
exist at the site in accordance with the requirements of 10 CFR 100.23 and of 10 CFR 50, Appendix S. If
noncapable surface faulting is present under foundations for safetyrelated structures, the COL
applicant will demonstrate that the faults have no significant impact on the structural integrity of
safetyrelated structures, systems, or components.
2.5.3
2.56
A COL applicant that references the U.S. EPR design certification will present sitespecific information
about the properties and stability of soils and rocks that may affect the nuclear power plant facilities
under both static and dynamic conditions, including the vibratory ground motions associated with the
CSDRS and the site specific SSE.
2.5.4
2.57
A COL applicant that references the U.S. EPR design certification will verify that the predicted
differential settlement value of ½ in per 50 ft in any direction across the foundation basemat of a
Seismic Category I structure is not exceeded. Settlement values larger than this may be demonstrated
acceptable by performing additional sitespecific evaluations.
2.5.4.10.2
2.58
A COL applicant that references the U.S. EPR design certification will evaluate sitespecific information
concerning the stability of earth and rock slopes, both natural and manmade (e.g., cuts, fill,
embankments, dams, etc.), of which failure could adversely affect the safety of the plant.
2.5.5
2.59
A COL applicant that references the U.S. EPR design certification will reconcile the site specific soil
properties with those used for design of U.S. EPR Seismic Category I structures and foundations
described in Section 3.8.
2.510
A COL applicant that references the U.S. EPR design certification will investigate and determine the
uniformity of the underlying layers of site specific soil conditions beneath the foundation basemats.
The classification of uniformity or nonuniformity will be established by a geotechnical engineer.
2.5.4.10.3
3.11
A COL applicant that references the U.S. EPR design certification will identify the sitespecific QA
Program Plan that demonstrates compliance with GDC1.
3.1.1.1.1
3.21
A COL applicant that references the U.S. EPR design certification will identify the seismic classification
of applicable sitespecific SSCs that are not identified in Table 3.2.21.
3.2.1
3.22
A COL applicant that references the U.S. EPR design certification will identify the quality group
classification of applicable sitespecific SSCs important to safety that are not identified in Table 3.2.21.
3.2.2
3.31
A COL applicant that references the U.S. EPR design certification will determine sitespecific wind and
tornado characteristics and compare these to the standard plant criteria. If the sitespecific wind and
tornado charactistics are not bounded by the site parameters, postulated for the certified design, then
the COL applicant will evaluate the design for sitespecific wind and tornado events and demonstrate
that these loadings will not adversely affect the ability of safetyrelated structures to perform their
safety functions during or after such events.
3.3
3.32
A COL applicant that references the U.S. EPR design certification will demonstrate that failure of
sitespecific structures or components not included in the U.S. EPR standard plant design, and not
designed for wind loads, will not affect the ability of other structures to perform their intended safety
functions.
3.3.1
3.33
A COL applicant that references the U.S. EPR design certification will demonstrate that failure of
sitespecific structures or components not included in the U.S. EPR standard plant design, and not
designed for tornado loads, will not affect the ability of other structures to perform their intended
safety functions.
3.3.2
3.41
A COL applicant that references the U.S. EPR design certification will confirm the potential site specific
external flooding events are bounded by the U.S. EPR design basis flood values or otherwise
demonstrate that the design is acceptable.
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3.4.3.2
Rev. 7
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Interfaces with Standard Designs and Early Site Permits
Table 1.8-2— FSAR Sections that Address COL Items
(Page 5 of 20)
Item No.
Description
Section
3.42
A COL applicant that references the U.S. EPR design certification will perform a flooding analysis for the
ultimate heat sink makeup water intake structure based on the sitespecific design of the structures
and the flood protection concepts provided herein.
3.4.3.10
3.43
A COL applicant that references the U.S. EPR design certification will define the need for a sitespecific
permanent dewatering system.
3.4.3.11
3.44
A COL applicant that references the U.S. EPR design certification will perform internal flooding analyses
prior to fuel load for the Safeguard Buildings and Fuel Building to demonstrate that the impact of
internal flooding is contained within the Safeguard Building or Fuel Building division of origin.
3.4.1
3.45
A COL applicant that references the U.S. EPR design certification will perform an internal flooding
analysis prior to fuel load for the Reactor Building and Reactor Building Annulus to demonstrate that
the essential equipment required for safe shutdown is located above the internal flood level.
3.4.1
3.46
A COL applicant that references the U.S. EPR design certification will include in its maintenance
program appropriate watertight door preventive maintenance in accordance with manufacturer
recommendations so that each Safeguards Building watertight door above elevation +0 feet remains
capable of performing its intended function.
3.4.1
3.47
A COL applicant that references the U.S. EPR design certification will design the watertight seal
between the Access Building and the adjacent Category I access path to the Reactor Building Tendon
Gallery. Watertight seal design will account for hydrostatic loads, lateral earth pressure loads, and other
applicable loads.
3.4.2
3.51
A COL applicant that references the U.S. EPR design certification will describe controls to confirm that
unsecured maintenance equipment, including that required for maintenance and that are undergoing
maintenance, will be removed from containment prior to operation, moved to a location where it is not
a potential hazard to SSCs important to safety, or seismically restrained to prevent it from becoming a
missile.
3.5.1.2.3
3.52
A COL applicant that references the U.S. EPR design certification will confirm the evaluation of the
probability of turbine missile generation for the selected turbine generator, P1, is less than 1 x 104 for
turbinegenerators favorably oriented with respect to containment.
3.5.1.3
3.53
A COL applicant that references the U.S. EPR design certification will assess the effect of potential
turbine missiles from turbine generators within other nearby or colocated facilities.
3.5.1.3
3.54
A COL applicant that references the U.S. EPR design certification will evaluate the potential for other
missiles generated by natural phenomena, such as hurricanes and extreme winds, and their potential
impact on the missile protection design features of the U.S. EPR.
3.5.1.4
3.55
A COL applicant that references the U.S. EPR design certification will evaluate the potential for site
proximity explosions and missiles generated by these explosions for their potential impact on missile
protection design features.
3.5.1.5
3.56
A COL applicant that references the U.S. EPR design certification will evaluate sitespecific aircraft
hazards and their potential impact on plant SSCs.
3.5.1.6
3.57
For sites with surrounding ground elevations higher than plant grade, a COL applicant that references
the U.S. EPR design certification will confirm that automobile missiles cannot be generated within a 0.5
mile radius of safetyrelated SSCs that would lead to impact higher than 30 ft above plant grade.
3.5.1.4
3.58
A COL applicant that references the U.S. EPR design certification will describe controls to confirm that
unsecured compressed gas cylinders will be either removed or seismically supported when not in use
to prevent them from becoming missiles.
3.5.1.1.3
3.59
A COL applicant that references the U.S. EPR design certification will describe controls to confirm that
unsecured maintenance equipment, including that required for maintenance and that are undergoing
maintenance, will be either removed or seismically supported when not in use to prevent it from
becoming a missile.
3.5.1.1.3
3.61
A COL applicant that references the U.S. EPR design certification will perform the pipe break hazards
analysis and reconcile deviations in the asbuilt configuration to the asdesigned analysis.
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3.6.1
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Interfaces with Standard Designs and Early Site Permits
Table 1.8-2— FSAR Sections that Address COL Items
(Page 6 of 20)
Item No.
Description
Section
3.62
A COL applicant that references the U.S. EPR design certification will perform the pipe break hazards
analysis and reconcile deviations in the asbuilt configuration to the asdesigned analysis.
3.6.2.1
3.63
A COL applicant that references the U.S. EPR design certification will confirm that the design LBB
analysis remains bounding for each piping system and provide a summary of the results of the actual
asbuilt plant specific LBB analysis, including material properties of piping and welds, stress analyses,
leakage detection capability, and degradation mechanisms.
3.6.3
3.64
A COL applicant that references the U.S. design certification will provide diagrams showing the final
asdesigned configurations, locations, and orientations of the pipe whip restraints in relation to break
locations in each piping system.
3.6.2.5.1
3.65
A COL applicant that references the U.S. EPR design certification will implement the ISI program as
augmented with NRC approved ASME Code cases that are developed and approved for augmented
inspections of Alloy 690/152/52 material to address PWSCC concerns.
3.6.3
3.71
A COL applicant that references the U.S. EPR design certification will confirm that the site specific
seismic response is within the parameters of section 3.7 of the U.S. EPR standard design.
3.7.2
3.72
A COL applicant that references the US EPR design certification will provide the sitespecific separation
distances for the access building and turbine building.
3.7.2.8
3.73
A COL applicant that references the U.S. EPR design certification will provide a description of methods
used for seismic analysis of sitespecific Category I concrete dams, if applicable.
3.7.3.13
3.74
A COL applicant that references the U.S. EPR design certification will determine whether essentially the
same seismic response from a given earthquake is expected at each of the units in a multiunit site or
instrument each unit. In the event that only one unit is instrumented, annunciation shall be provided
to each control room.
3.7.4.2
3.75
A COL applicant that references the U.S. EPR design certification will determine a location for the
freefield acceleration sensor such that the effects associated with surface features, buildings, and
components on the recordings of ground motion are insignificant. The acceleration sensor must be
based on material representative of that upon which the Nuclear Island (NI) and other Seismic Category
I structures are founded.
3.7.4.2.1
3.76
A COL applicant that references the US EPR design certification will provide the seismic design basis for
the sources of fire protection water supply for safe plant shutdown in the event of a SSE.
3.7.2.8
3.77
A COL applicant that references the U.S. EPR design certification will demonstrate that the response of
the Access Building to an SSE event will not impair the ability of Seismic Category I systems, structures,
or components to perform their design basis safety functions.
3.7.2.8
3.78
A COL applicant that references the U.S. EPR design certification will demonstrate that the response of
the TB (including Switchgear Building on the common basemat) to an SSE event will not impair the
ability of Seismic Category I systems, structures, or components to perform their design basis safety
functions.
3.7.2.8
3.81
A COL applicant that references the U.S. EPR design certification will confirm that site specific loads lie
within the standard plant design envelope for the Reactor Containment Building, or perform additional
analyses to verify structural adequacy.
3.8.1.3
3.82
A COL applicant that references the U.S. EPR design certification will describe any differences between
the standard plant layout and design of Seismic Category I structures required for sitespecific
conditions.
3.8.4.1
3.83
A COL applicant that references the U.S. EPR design certification will confirm that site specific loads lie
within the standard design envelope for other Seismic Category I structures, or perform additional
analyses to verify structural adequacy.
3.8.4.3
3.84
A COL applicant that references the U.S. EPR design certification will provide a description of Seismic
Category I buried conduit and duct banks.
3.8.4.1.8
3.85
A COL applicant that references the U.S. EPR design certification will provide a description of Seismic
Category I buried pipe and pipe ducts.
3.8.4.1.9
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Table 1.8-2— FSAR Sections that Address COL Items
(Page 7 of 20)
Item No.
Description
Section
3.86
A COL applicant that references the U.S. EPR design certification will confirm that site specific loads lie
within the standard design envelope for RB internal structures, or perform additional analyses to verify
structural adequacy.
3.8.3.3
3.87
A COL applicant that references the U.S. EPR design certification will confirm that sitespecific
conditions for Seismic Category I buried conduit, electrical duct banks, pipe, and pipe ducts satisfy the
requirements specified in Section 3.8.4.4.5 and those specified in AREVA NP Topical Report
ANP10264NPA.
3.8.4.5
3.88
A COL applicant that references the U.S. EPR design certification will address sitespecific Seismic
Category I structures that are not described in this section.
3.8.4.1
3.89
A COL applicant that references the U.S. EPR design certification will describe sitespecific foundations
for Seismic Category I structures that are not described in this section.
3.8.5.1
3.810
A COL applicant that references the U.S. EPR design certification will evaluate sitespecific methods for
shear transfer between the foundation basemats and underlying soil for sitespecific soil characteristics
that are not within the envelope of the soil parameters specified in Section 2.5.4.2.
3.8.5.5
3.811
A COL applicant that references the U.S. EPR design certification will evaluate the use of epoxy coated
rebar for foundations subjected to aggressive environments, as defined in ACI 34901, Chapter 4. In
addition, the waterproofing system of all Seismic Category I foundations subjected to aggressive
environments will be evaluated for use in aggressive environments. Also, the concrete of Seismic
Category I foundations subjected to aggressive environments will meet the durability requirements of
ACI 34901, Chapter 4 or ASME, Section III, Division 2, Article CC2231.7, as applicable.
3.8.5.6.1
3.812
A COL applicant that references the U.S. EPR design certification will describe the program to examine
inaccessible portions of belowgrade concrete structures for degradation and monitoring of
groundwater chemistry.
3.8.5.7
3.813
A COL applicant that references the U.S. EPR design certification will identify if any sitespecific
settlement monitoring requirements are required for Seismic Category I foundations based on
sitespecific soil conditions.
3.8.5.7
3.814
A COL applicant that references the U.S. EPR design certification will describe the design and analysis
procedures used for buried conduit and duct banks, and buried pipe and pipe ducts.
3.8.4.4.5
3.815
A COL applicant that references the U.S. EPR design certification will use results from site specific
investigations to determine the routing of buried pipe and pipe ducts.
3.8.4.4.5
3.816
A COL applicant that references the U.S. EPR design certification will perform geotechnical engineering
analyses to determine if the surface load will cause lateral and/or vertical displacement of bearing soil
for the buried pipe and pipe ducts and consider the effect of wide or extra heavy loads.
3.8.4.4.5
3.91
A COL applicant that references the U.S. EPR design certification will submit the results from the
vibration assessment program for the U.S. EPR RPV internals, and piping systems specified in U.S. EPR
FSAR Tier 2, Section 3.9.2.1, in accordance with RG 1.20.
3.9.2.4
3.92
A COL applicant that references the U.S. EPR design certification will prepare the design specifications
and design reports for ASME Class 1, 2, and 3 components, piping, supports and core support
structures that comply with and are certified to the requirements of Section III of the ASME Code. The
COL applicant will address the results and conclusions from the reactor internals material reliability
programs applicable to the U.S. EPR reactor internals with regard to known aging degradation
mechanisms such as irradiationassisted stress corrosion cracking and void swelling.
3.9.3
3.93
A COL applicant that references the U.S. EPR design certification will examine the feedwater line welds
after hot functional testing prior to fuel loading and at the first refueling outage, in accordance with
NRC Bulletin 7913. A COL applicant that references the U.S. EPR design certification will report the
results of inspections to the NRC, in accordance with NRC Bulletin 7913.
3.9.3.1.1
3.94
As noted in ANP10264NPA, A COL applicant that references the U.S. EPR design certification will
confirm that thermal deflections do not create adverse conditions during hot functional testing.
3.9.3.1.1
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Table 1.8-2— FSAR Sections that Address COL Items
(Page 8 of 20)
Item No.
Description
Section
3.95
As noted in ANP10264NPA, should a COL applicant that references the U.S. EPR design certification
find it necessary to route Class 1, 2, and 3 piping not included in the U.S. EPR design certification so that
it is exposed to wind and tornadoes, the design must withstand the plant designbasis loads for this
event.
3.9.3.1.1
3.96
A COL applicant that references the US EPR design certification will identify any additional sitespecific
valves in Table 3.9.62 to be included within the scope of the IST program.
3.9.6.3
3.97
A COL applicant that references the U.S. EPR design certification will submit the preservice testing (PST)
program and IST program for pumps, valves, and snubbers as required by 10 CFR 50.55a.
3.9.6
3.98
A COL applicant that references the US EPR design certification will identify any additional sitespecific
pumps in Table 3.9.61 to be included within the scope of the IST program.
3.9.6.2
3.99
COL applicant that references the U.S. EPR design certification will either use a piping analysis program
based on the computer codes described in Section 3.9.1 and Appendix 3C or will implement a U.S. EPR
benchmark program using models specifically selected for the U.S. EPR.
3.9.1.2
3.910
Pipe stress and support analysis will be performed by a COL applicant that references the U.S. EPR
design certification.
3.9.1.2
3.911
A COL applicant that references the U.S. EPR design certification will provide a summary of the
maximum total stress, deformation (where applicable), and cumulative usage factor values for each of
the component operating conditions for ASME Code Class 1 components. For those values that differ
from the allowable limits by less than 10 percent, the COL applicant will provide the contribution of
each of the loading categories (e.g., seismic, pipe rupture, dead weight, pressure, and thermal) to the
total stress for each maximum stress value identified in this range.
The COL applicant will also provide the maximum total stress and deformation values for each
operating condition for Class 2 & 3 components required for safe shutdown of the reactor, or
mitigation of consequences of a postulated piping failure without offsite power. Identification of those
values that differ from the allowable limits by less than 10 percent will also be provided.
3.9.3.1
3.912
A COL applicant that references the U.S.EPR design certification will provide a table identifying the
safetyrelated systems and components that use snubbers in their support systems, including the
number of snubbers, type (hydraulic or mechanical), applicable standard, and function (shock,
vibration, or dualpurpose snubber). For snubbers identified as either a dualpurpose or vibration
arrester type, the COL applicant shall indicate whether the snubber or component was evaluated for
fatigue strength.
3.9.6.4
3.913
A COL applicant that references the U.S. EPR design certification will identify the implementation
milestones and applicable ASME OM Code for the preservice and inservice examination and testing
programs. These programs will be consistent with the requirements in the latest edition and addenda
of the OM Code incorporated by reference in 10 CFR 50.55a on the date 12 months before the date for
initial fuel load.
3.9.6
3.914
A COL applicant that references the U.S. EPR design certification will provide a summary of reactor core
support structure maximum total stress, deformation, and cumulative usage factor values for each
component and each operating condition in conformance with ASME Section III Subsection NG.
3.9.5.2
3.101
A COL applicant that references the U.S. EPR design certification will create and maintain the SQDP file
during the equipment selection and procurement phase.
3.10.4
3.102
A COL applicant that references the U.S. EPR design certification will identify any additional site specific
components that need to be added to the equipment list in Table 3.101.
3.10.1.1
3.103
If the seismic and dynamic qualification testing is incomplete at the time of the COL application, A COL
applicant that references the U.S. EPR design certification will submit an implementation program,
including milestones and completion dates, for NRC review and approval prior to installation of the
applicable equipment.
3.10.4
3.111
A COL applicant that references the U.S. EPR design certification will maintain the equipment
qualification test results and qualification status file during the equipment selection, procurement
phase and throughout the installed life in the plant.
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3.11
Rev. 7
FSAR: Chapter 1.0
Interfaces with Standard Designs and Early Site Permits
Table 1.8-2— FSAR Sections that Address COL Items
(Page 9 of 20)
Item No.
Description
Section
3.112
A COL applicant that references the U.S. EPR design certification will identify additional site specific
components that need to be added to the environmental qualification list in Table 3.111.
3.113
If the equipment qualification testing is incomplete at the time of the COL application, a COL applicant
that references the U.S. EPR design certification will submit an implementation program, including
milestones and completion dates, for NRC review and approval prior to installation of the applicable
equipment.
3.11.3
3.121
A COL applicant that references the U.S. EPR design certification will perform a review of the impact of
contributing mass of supports on the piping analysis following the final support design to confirm that
the mass of the support is no more than ten percent of the mass of the adjacent pipe span.
3.12.4.2
3.122
As indicated in Section 5.3 of topical report ANP10264NPA, pipe and support stress analysis will be
performed by the COL applicant that references the U.S. EPR design certification. If the COL applicant
that references the U.S. EPR design certification chooses to use a piping analysis program other than
those listed in Section 5.1 of the topical report, the COL applicant will implement a benchmark
program using models specifically selected for the U.S. EPR.
3.12.4.3
3.123
A COL applicant that references the U.S. EPR design certification will monitor the RHR/SIS/ EBS injection
piping from the RCS to the first isolation valve (all four trains), and RHR/SIS suction piping from the RCS
to the first isolation valve (trains 1 and 4) during the first cycle of the first U.S. EPR initial plant operation
to verify that operating conditions have been considered in the design unless data from a similar
plant’s operation demonstrates that thermal oscillation is not a concern for piping connected to the
RCS.
3.12.5.9
3.124
A COL applicant that references the U.S. EPR design certification will monitor pressurizer surge line
temperatures during the first fuel cycle of initial plant operation to verify that the design transients for
the surge line are representative of actual plant operations.
3.12.5.10.1
3.125
A COL applicant that references the U.S. EPR design certification will monitor the normal spray line
temperatures during the first cycle of the first U.S. EPR initial plant operation to verify that the design
transients for the normal spray are representative of actual plan operations unless data from a similar
plant’s operation determines that monitoring is not warranted.
3.12.5.10.3
3.126
A COL applicant that references the U.S. EOR design certification will monitor the temperature of the
main feedwater lines during the first cycle of the first U.S. EPR initial plant operation to verify that the
design transients for the main feedwater lines are representative of actual plant operations unless data
from a similar plant’s operation determines that monitoring is not warranted.
3.12.5.10.4
3.131
A COL applicant referencing the U.S. EPR design certification will submit the inservice inspection
program for ASME Code Class 1, Class 2, and Class 3 threaded fasteners, to the NRC prior to performing
the first inspection. The program will identify the applicable edition and addenda of ASME Section XI
and ensure compliance with the requirements of 10 CFR 50.55a(b)(2)(xxvii).
3.13.2
3E1
A COL applicant that references the U.S. EPR design certification will address critical sections relevant to
sitespecific Seismic Category I structures.
3E
5.21
Deleted
5.22
A COL applicant that references the U.S. EPR design certification will identify additional ASME code
cases to be used.
5.23
A COL applicant that references the U.S. EPR design certification will identify the implementation
milestones for the sitespecific ASME Section XI preservice and inservice inspection program for the
reactor coolant pressure boundary, consistent with the requirements of 10 CFR 50.55a (g). The program
will identify the applicable edition and addenda of the ASME Code Section XI, and will identify
additional relief requests and alternatives to Code requirements.
5.2.4
5.24
A COL applicant that references the U.S. EPR design certification will develop procedures in accordance
with RG 1.45, Revision 1.
5.2.5
5.31
A COL applicant that references the U.S. EPR design certification will identify the implementation
milestones for the material surveillance program.
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Table 1.8-2— FSAR Sections that Address COL Items
(Page 10 of 20)
Item No.
Description
Section
5.32
A COL applicant that references the U.S. EPR design certification will provide a plantspecific pressure
and temperature limits report (PTLR), consistent with an approved methodology.
5.3.2.1
5.33
A COL applicant that references the U.S. EPR design certification will provide plantspecific RTPTS values
in accordance with 10 CFR 50.61 for vessel beltline materials.
5.3.2.3
5.34
A COL Applicant that references the U.S. EPR design certification will provide plant specific surveillance
data to benchmark BAW2241PA and demonstrate applicability to the specific plant.
5.3.1.6
5.41
A COL applicant that references the U.S. EPR design certification will identify the edition and addenda
of ASME Section XI applicable to the site specific Steam Generator inspection program.
5.4.2.5.2.2
6.11
A COL applicant that references the U.S. EPR design certification will review the fabrication and welding
procedures and other QA methods of ESF component vendors to verify conformance with RGs 1.44 and
1.31.
6.1.1.1
6.12
If components cannot be procured with DBAqualified coatings applied by the component
manufacturer, A COL applicant that references the U.S. EPR design certification must do one of the
following: procure the component as uncoated and apply a DBAqualified coating system in
accordance with 10 CFR 50 Appendix B, Criterion IX; confirm that the DBAunqualified coating is
removed and the component is recoated with DBAqualified coatings in accordance with 10 CFR 50
Appendix B, Criterion IX; or add the quantity of DBAunqualified coatings to a list that documents those
DBAunqualified coatings already existing within containment.
6.1.2.3.2
6.21
A COL applicant that references the U.S. EPR design certification will identify the implementation
milestones for the CLRT program described under 10 CFR 50, Appendix J.
6.31
A COL applicant that references the U.S. EPR design certification will describe the containment
cleanliness program which limits debris within containment.
6.41
A COL applicant that references the U.S. EPR design certification will identify the type(s) of Seismic
Category I Class IE toxic gas sensors (i.e., the toxic chemical(s) of concern) necessary for control room
operator protection.
6.4.6
6.42
A COL applicant that references the U.S. EPR design certification will provide written emergency
planning and procedures in the event of a radiological or a hazardous chemical release within or near
the plant, and will provide training of control room personnel.
6.4.3
6.43
A COL applicant that references the U.S. EPR design certification will evaluate the results of the toxic
chemical accidents from Section 2.2.3 and address their impact on control room habitability in
accordance with RG 1.78.
6.4.4
6.44
A COL applicant that references the U.S. EPR design certification will confirm that the radiation
exposure of main control room occupants resulting from a design basis accident at a nearby unit on a
multiunit site is bounded by the radiation exposure from the postulated design basis accidents
analyzed for the U.S. EPR; or confirm that the limits of GDC19 are met.
6.4.4
6.61
A COL applicant that references the U.S. EPR design certification will identify the implementation
milestones for the sitespecific ASME Section XI preservice and inservice inspection program for the
Class 2 and Class 3 components, consistent with the requirements of 10 CFR 50.55a (g). The program
will identify the applicable edition and addenda of the ASME Code Section XI, and will identify
additional relief requests and alternatives to Code requirements.
6.6
7.11
A COL applicant that references the U.S. EPR design certification will update the initial inventory list of
accident monitoring variables including variable types in Table 7.51 Initial Inventory of PostAccident
Monitoring Variables, with a final list upon completion of the emergency procedure guidelines or the
emergency operating and abnormal operating procedures prior to fuel loading.
8.11
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
describing the interface between the offsite transmission system, and the nuclear unit, including
switchyard interconnections.
8.1.1
8.12
A COL applicant that references the U.S. EPR design certification will identify sitespecific loading
differences that raise EDG or Class 1E battery loading, and demonstrate the electrical distribution
system is adequately sized for the additional load.
8.1.3
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Table 1.8-2— FSAR Sections that Address COL Items
(Page 11 of 20)
Item No.
Description
Section
8.21
A COL applicant that references the U.S. EPR design certification will provide site specific information
regarding the offsite transmission system and their connections to the station switchyard.
8.2.1.1
8.22
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
for the switchyard layout design.
8.2.1.2
8.23
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
that identifies actions necessary to restore offsite power and use available nearby power sources when
offsite power is unavailable.
8.2.2.7
8.24
A COL applicant that references the U.S. EPR design certification will provide a sitespecific grid stability
analysis.
8.2.2.4
8.25
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
for the protective devices that control the switchyard breakers and other switchyard relay devices.
8.2.1.2
8.26
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
for the station switchyard equipment inspection and testing plan.
8.2.2.5
8.27
A COL applicant that references the U.S. EPR design certification will provide site specific information
regarding the communication agreements and protocols between the station and the transmission
system operator, independent system operator, or reliability coordinator/authority. Additionally, the
applicant will provide a description of the analysis tool used by the transmission system operator to
determine, in real time, the impact that the loss or unavailability of various transmission system
elements will have on the condition of the transmission system to provide posttrip voltages at the
switchyard. The information provided will be consistent with information requested in NRC Generic
Letter 200602.
8.2.1.1
8.28
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
regarding indication and control of switchyard components.
8.2.1.2
8.31
A COL applicant that references the U.S. EPR design certification will monitor and maintain EDG
reliability during plant operations to verify the selected reliability level target is being achieved as
intended by RG 1.155.
8.3.1.1.5
8.32
A COL applicant that references the U.S. EPR design certification will describe inspection, testing and
monitoring programs to detect the degradation of inaccessible or underground power cables that
support EDGs, offsite power, ESW and other systems that are within the scope of 10 CFR 50.65.
8.3.1.1.8
8.41
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
that identifies any additional local power sources and transmission paths that could be made available
to resupply the power plant following a LOOP.
8.42
A COL applicant that references the U.S. EPR design certification will address the RG 1.155 guidance
related to procedures and training to cope with SBO.
8.4.2.6.4
9.11
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
on the heavy load handling program, including a commitment to procedures for heavy load lifts in the
vicinity of irradiated fuel or safe shutdown equipment, and crane operator training and qualification.
9.1.5.2.5
9.21
A COL applicant that references the U.S. EPR design certification will provide site specific information
for the UHS support systems such as makeup water, blowdown, and chemical treatment (to control
biofouling).
9.22
A COL applicant that references the U.S. EPR design certification will provide sitespecific details related
to the sources and treatment of makeup to the potable and sanitary water system along with a
simplified piping and instrument diagram.
9.2.4.2.1
9.23
The raw water supply system (RWSS) and the design requirements of the RWSS are site specific and will
be addressed by the COL applicant.
9.2.9
9.24
A COL applicant that references the U.S. EPR design certification will provide a description of materials
that will be used for the essential service water system (ESWS) at their site location, including the basis
for determining that the materials being used are appropriate for the site location and for fluid
properties that apply
9.2.1.3.5
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Interfaces with Standard Designs and Early Site Permits
Table 1.8-2— FSAR Sections that Address COL Items
(Page 12 of 20)
Item No.
Description
Section
9.25
A COL applicant that references the U.S. EPR design certification will provide a description of materials
that will be used for the UHS at their site location, including the basis for determining that the materials
being used are appropriate for the site location and for the fluid properties that apply.
9.2.5.2
9.41
A COL applicant that references the U.S. EPR design certification will provide sitespecific design
information for the turbine building ventilation system (TBVS).
9.4.4
9.42
A COL applicant that references the U.S. EPR design certification will provide sitespecific design
information for the switchgear building ventilation system, turbine island (SWBVS).
9.4.4
9.51
A COL applicant referencing the U.S. EPR certified design will identify additional site specific
communication locations necessary to support effective communication between plant personnel in
all vital areas of the plant during normal operation, as well as during accident conditions.
9.52
A COL applicant that references the U.S. EPR design certification will submit site specific information to
address the Regulatory Guide 1.189, Regulatory Position C.1.7.1, Design and Procurement Document
Control.
Table 9.5-1,
C.1.7.1
9.53
A COL applicant that references the U.S. EPR design certification will submit site specific information to
address the Regulatory Guide 1.189, Regulatory Position C.1.7.2, Instructions, Procedures and
Drawings.
Table 9.5-1,
C.1.7.2
9.54
A COL applicant that references the U.S. EPR design certification will submit site specific information to
address the Regulatory Guide 1.189, Regulatory Position C.1.7.3, Control of Purchased Material,
Equipment, and Services.
Table 9.5-1,
C.1.7.3
9.55
A COL applicant that references the U.S. EPR design certification will submit site specific information to
address the Regulatory Guide 1.189, Regulatory Position C.1.8, Fire Protection Program Changes/Code
Deviations.
Table 9.5-1,
C.1.8
9.56
A COL applicant that references the U.S. EPR design certification will submit site specific information to
address the Regulatory Guide 1.189, Regulatory Position C.1.8.1, Change Evaluations.
Table 9.5-1,
C.1.8.1
9.57
A COL applicant that references the U.S. EPR design certification will submit site specific information to
address the Regulatory Guide 1.189, Regulatory Position C.1.8.5, 10 CFR 50.72 Notification and 10 CFR
50.73 Reporting.
Table 9.5-1,
C.1.8.5
9.58
A COL applicant that references the U.S. EPR design certification will submit site specific information to
address the Regulatory Guide 1.189, Regulatory Position C.1.8.7, Fire Modeling.
Table 9.5-1,
C.1.8.7
9.59
A COL applicant that references the U.S. EPR design certification will submit site specific information to
address the Regulatory Guide 1.189, Regulatory Position C.5.5, PostFire SafeShutdown Procedures.
Table 9.5-1,
C.5.5
9.510
A COL applicant that references the U.S. EPR design certification will submit site specific information to
address the Regulatory Guide 1.189, Regulatory Position C.5.5.1, SafeShutdown Procedures.
Table 9.5-1,
C.5.5.1
9.511
A COL applicant that references the U.S. EPR design certification will submit site specific information to
address the Regulatory Guide 1.189, Regulatory Position C.5.5.2, Alternative/ Dedicated Shutdown
Procedures.
Table 9.5-1,
C.5.5.2
9.512
A COL applicant that references the U.S. EPR design certification will submit site specific information to
address the Regulatory Guide 1.189, Regulatory Position C.5.5.3, Repair Procedures.
Table 9.5-1,
C.5.5.3
9.513
A COL applicant that references the U.S. EPR design certification will submit site specific information to
address the Regulatory Guide 1.189, Regulatory Position C.6.2.4, Independent Spent Fuel Storage
Areas.
Table 9.5-1,
C.6.2.4
9.514
A COL applicant that references the U.S. EPR design certification will submit site specific information to
address the Regulatory Guide 1.189, Regulatory Position C.6.2.6, Cooling Towers.
9.5.1.2.1
9.515
A COL applicant that references the U.S. EPR design certification will submit site specific information to
address Regulatory Guide 1.189, Regulatory Position C.7.6, Nearby Facilities.
Table 9.5-1,
C.7.6
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Table 1.8-2— FSAR Sections that Address COL Items
(Page 13 of 20)
Item No.
Description
Section
9.516
A COL applicant that references the U.S. EPR design certification will perform an asbuilt, postfire Safe
Shutdown Analysis, which includes final plant cable routing, fire barrier ratings, purchased equipment,
equipment arrangement and includes a review against the assumptions and requirements contained
in the Fire Protection Analysis. The postfire Safe Shutdown Analysis will demonstrate that safe
shutdown performance objectives are met prior to fuel loading and will include a postfire safe
shutdown circuit analysis based on the methodology described in NEI 0001, ”Guidance for PostFire
SafeShutdown Circuit Analysis.”
9.5.1.2.1
9.517
A COL applicant that references the U.S. EPR design certification will evaluate the differences between
the asdesigned and asbuilt plant configuration to confirm the Fire Protection Analysis remains
bounding. This evaluation will be performed prior to fuel loading and will consider the final plant cable
routing, fire barrier ratings, combustible loading, ignition sources, purchased equipment, equipment
arrangement and includes a review against the assumptions and requirements contained in the Fire
Protection Analysis. The applicant will describe how this asbuilt evaluation will be performed and
documented, and how the NRC will be made aware of deviations from the FSAR, if any.
9.5.1.3
9.518
A COL applicant that references the U.S. EPR design certification will perform a supplemental Fire
Protection Analysis for sitespecific areas of the plant not analyzed bv the FSAR.
9.5.1.3
9.519
A COL applicant that references the U.S. EPR design certification will provide a description and
simplified Fire Protection System piping and instrumentation diagrams for sitespecific systems.
9.5.1.2.1
9.520
A COL applicant that references the U.S. EPR design certification will describe the program used to
monitor and maintain an acceptable level of quality in the fire protection system freshwater storage
tanks.
9.5.1.2.1
9.521
A COL applicant that references the U.S. EPR design certification will provide a description of the offsite
communication system that interfaces with the onsite communication system, including type of
connectivity, radio frequency, normal and backup power supplies and plant security system interface.
9.5.2.1.1
9.5.4.4
9.522
A COL applicant that references the U.S. EPR design certification will describe the sitespecific sources
of acceptable fuel oil available for refilling the EDG fuel oil storage tanks within seven days, including
the means of transporting and refilling the fuel storage tanks, following a design basis event to enable
each diesel generator system to supply uninterrupted emergency power.
10.01
Deleted
10.21
Deleted
10.22
A COL applicant that references the U.S. EPR design certification will provide applicable material
properties of the turbine rotor, including the method of calculating the fracture toughness properties,
after the site specific turbine has been procured.
10.2.3.1
10.23
A COL applicant that references the U.S. EPR design certification will provide applicable turbine disk
rotor specimen test data, load displacement data from the compact tension specimens and the
fracture toughness properties after the sitespecific turbine has been procured.
10.2.3.2
10.24
A COL applicant that references the U.S. EPR design certification will provide schematics and logic
diagrams for the turbine control system.
10.2.2.5
10.25
A COL applicant that references the U.S. EPR design certification will provide the sitespecific turbine
rotor inservice inspection program and inspection interval consistent with the manufacturer’s turbine
missile analysis.
10.2.3.6
10.31
A COL applicant that references the U.S. EPR design certification will identify the authority responsible
for implementation and management of the secondary side water chemistry program.
10.3.5
10.32
A COL applicant that references the U.S. EPR design certification will develop and implement a FAC
condition monitoring program that is consistent with Generic Letter 8908 and NSAC202LR3 for the
carbon steel portions of the steam and power conversion systems that contain water or wet steam
prior to initial fuel loading.
10.3.6.3
10.41
A COL applicant that references the U.S. EPR design certification will describe the sitespecific main
condenser materials.
10.4.1.2
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Item No.
Description
Section
10.42
A COL applicant that references the U.S. EPR design certification will describe the sitespecific design
pressure and test pressure for the main condenser.
10.43
A COL applicant that references the U.S. EPR design certification will provide the description of the
sitespecific portions of the CWS.
10.4.5.2.1
10.44
A COL applicant that references the U.S. EPR design certification will provide the specific chemicals
used within the chemical treatment system as determined by the sitespecific water conditions.
10.4.5.2.2
10.45
A COL applicant that references the U.S. EPR design certification will provide the sitespecific CWS
piping design pressure.
10.4.5.2.2
10.46
If a vacuum priming system is required, a COL applicant that references the U.S. EPR design certification
will provide the sitespecific information.
10.4.5.2.2
10.47
A COL applicant that references the U.S. EPR design certification will provide information to address the
potential for flooding of safetyrelated equipment due to failures of the sitespecific CWS.
10.4.5.3
11.21
A COL applicant that references the U.S. EPR design certification will perform a sitespecific liquid waste
management system costbenefit analysis.
11.2.4
11.22
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
on the release pathway, including a detailed description of the discharge path and plant sources of
dilution, the discharge flow rate, and dilution factors at or beyond the point of discharge.
11.23
A COL applicant that references the U.S. EPR design certification will confirm that the sitespecific
parameters are bounded by those provided in Table 11.25 and the dose pathways provided in Section
11.2.3.4.1. For sitespecific parameters that are not bounded by the values provided in Table 11.25 and
dose pathways other than those provided in Section 11.2.3.4.1, a COL applicant that references the U.S.
EPR design certification will perform a sitespecific liquid pathway dose analysis following the guidance
provided in RG 1.109 and RG 1.113, and compare the doses to the numerical design objectives of 10
CFR Part 50, Appendix I and demonstrate compliance with requirements of 10 CFR Part 20.1302 and 40
CFR Part 190.
11.2.3.4.2
11.24
A COL applicant that references the U.S. EPR design certification will confirm that the sitespecific
annual average liquid effluent concentrations are bounded by those specified in Table 11.27. For
sitespecific annual average liquid effluent concentrations that exceed the values provided in Table
11.27, a COL applicant that references the U.S. EPR design certification will demonstrate that the
annual average liquid effluent concentrations for expected and design basis conditions meet the limits
of 10 CFR Part 20, Appendix B, Table 2 in unrestricted areas.
11.2.3.5
11.25
A COL applicant that references the U.S. EPR design certification will confirm that the sitespecific data
(such as distance from release location to unrestricted area, contaminant migration time, and
dispersion and dilution in surface or ground water) are bounded by those specified in Section 11.2.3.7.
For sitespecific parameters that exceed the values provided in Section 11.2.3.7, a COL applicant that
references the U.S. EPR design certification will provide a sitespecific analysis to demonstrate that the
resulting water concentrations in the unrestricted area would meet the concentration limits of 10 CFR
Part 20, Appendix B, Table 2 using the guidance provided in SRP Sections 2.4.12, 2.4.13, 11.2 and BTP
116.
11.2.3.7
11.26
A COL applicant that references the U.S. EPR design certification and that chooses to install and operate
mobile skidmounted processing systems connected to permanently installed LWMS processing
equipment will include plant and sitespecific information describing how design features and
implementation of operating procedures for the LWMS will address the requirements of 10 CFR Part
20.1406(b) and guidance of SRP Section 11.2, RG 4.21 and 1.143, IE Bulletin 8010, and NEI 0808.
11.2.1.2.4
11.31
A COL applicant that references the U.S. EPR design certification will perform a sitespecific gaseous
waste management system costbenefit analysis.
11.32
A COL applicant that references the U.S. EPR design certification will provide a discussion of the onsite
vent stack design parameters and sitespecific release point characteristics.
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Table 1.8-2— FSAR Sections that Address COL Items
(Page 15 of 20)
Item No.
Description
Section
11.33
A COL applicant that references the U.S. EPR design certification will confirm that the sitespecific
parameters are bounded by those provided in Table 11.34 and the dose pathways provided in Section
11.3.3.4. For sitespecific parameters that are not bounded by the values provided in Table 11.34 and
dose pathways other than those provided in Section 11.3.3.4, a COL applicant that references the U.S.
EPR design certification will perform a sitespecific gaseous pathway dose analysis following the
guidance provided in RG 1.109 and RG 1.111, and compare the doses to the numerical design
objectives of 10 CFR Part 50, Appendix I and demonstrate compliance with requirements of 10 CFR Part
20.1302 and 40 CFR Part 190.
11.3.3.4
11.34
A COL applicant that references the U.S. EPR design certification will confirm that the sitespecific
annual average gaseous effluent concentrations are bounded by those specified in Table 11.36. For
sitespecific annual average gaseous effluent concentrations that exceed the values provided in Table
11.36, a COL applicant that references the U.S. EPR design certification will demonstrate that the
annual average gaseous effluent concentrations for expected and design basis conditions meet the
limits of 10 CFR Part 20, Appendix B, Table 2 in unrestricted areas.
11.3.3.5
11.35
A COL applicant that references the U.S. EPR design certification will confirm that the sitespecific
accident atmospheric dispersion data is bounded by the values provided in Table 2.11. For
sitespecific accident atmospheric dispersion data that exceed the values provided in Table 2.11, a
COL applicant that references the U.S. EPR design certification will provide a sitespecific analysis
demonstrating that the resulting dose at the exclusion area boundary associated with a radioactive
release due to gaseous waste system leak or failure does not exceed 0.1 rem in accordance with SRP
Section 11.3, BTP 115.
11.3.3.6
11.36
A COL applicant that references the U.S. EPR design certification and that chooses to install and operate
mobile skidmounted processing systems connected to permanently installed GWMS processing
equipment will include plant and sitespecific information describing how design features and
implementation of operating procedures for the GWMS will address the requirements of 10 CFR Part
20.1406(b) and guidance of SRP Section 11.3, RG 4.21, RG 1.143, IE Bulletin 8010, and NEI 0808.
11.3.1.2.4
11.41
A COL Applicant that references the U.S. EPR design certification will fully describe, at the functional
level, elements of the Process Control Program (PCP). This program description will identify the
administrative and operational controls for waste processing process parameters and surveillance
requirements which demonstrate that the final waste products meet the requirements of applicable
federal, state, and disposal site waste form requirements for burial at a 10 CFR 61 licensed low level
disposal site, toxic or hazardous waste requirements per 10 CFR 20.2007, and will be in accordance with
the guidance provided in RG 1.21, NUREG0800 Branch Technical Position 113, ANSI/ANS55.11992,
and Generic Letters 8009, 8138, and 8139. NEI 0710A PCP Template is an alternate means of
demonstrating compliance with GL 8901 and SECY 050197 until a plant specific PCP is developed
under license conditions.
11.4.3
11.42
A COL applicant that references the U.S. EPR design certification and that chooses to install and operate
mobile skidmounted processing systems connected to permanently installed solid waste
management system (SWMS) processing equipment will include plant and sitespecific information
describing how design features and implementation of operating procedures for the SWMS will
address the requirements of 10 CFR Part 20.1406(b) and guidance of SRP Section 11.4, Regulatory
Guides 4.21 and 1.143, IE Bulletin 8010, industry standards, and NEI 0808.
11.4.1
11.43
A COL applicant that references the U.S. EPR design certification will address plantspecific
commitments to address the longterm storage of LLRW beyond the provisions described in the U.S.
EPR design certification when such storage capacity is exhausted and describe how additional onsite
LLRW storage or alternate LLRW storage will be integrated in plant operations. To address the need for
additional storage, the commitment will address the requirements of 10 CFR Part 20, Appendix B (Table
2, Column 1 and 2); dose limits of 10 CFR 20.1301, 20.1302, and 20.1301(e) in unrestricted areas; Part
20.1406(b) in minimizing the contamination of plant facilities and environs; and design objectives of
Sections II.A, II.B, II.C, and II.D of Appendix I to 10 CFR Part 50. The design and operations of additional
onsite storage capacity will be integrated in the plantspecific process control program and consider
the guidance of SRP Section 11.4 and Appendix 11.4A, Regulatory Guides 1.206, 4.21 and 1.143, IE
Bulletin 8010, industry standards, and NEI 0808
11.4.1
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Table 1.8-2— FSAR Sections that Address COL Items
(Page 16 of 20)
Item No.
Description
Section
11.51
A COL applicant that references the U.S. EPR design certification will fully describe, at the functional
level, elements of the process and effluent monitoring and sampling programs required by 10 CFR Part
50 Appendix I, and 10 CFR 52.79 (a)(16). This program description, Offsite Dose Calculation Manual
(ODCM), will specify how a licensee controls, monitors, and performs radiological evaluations of
releases. The program will also document and report radiological effluents discharged to the
environment. NEI 0709A is an alternate means of demonstrating compliance with GL 8901 and SECY
050197 until a plant and sitespecific ODCM is developed under a license condition. NEI 079A is an
alternate means of demonstrating compliance with GL 8901 and SECY 050197 until a plant and
sitespecific ODCM is developed under a license condition.
11.5.2
11.52
A COL applicant that references the U.S. EPR design certification and that chooses to install and operate
skidmounted radiation monitoring and sampling systems connected to permanently installed
radioactive process and waste management systems will include plantspecific information describing
how design features and implementation of operating procedures for the PERMSS will address the
requirements of 10 CFR Part 20.1406(b) and guidance of SRP Section 11.5, Regulatory Guides 4.21 and
1.143, IE Bulletin 8010, ANSI/HPS13.11999 and ANSI N42.182004, and NEI 0808.
11.5.1
11.53
A COL applicant that references the U.S. EPR design certification is responsible for deriving PERMSS
subsystem’s lower limits of detection or detection sensitivities, and setpoints (alarms and process
termination/diversion) for liquid and gaseous process radiation monitoring equipment not covered by
the ODCM based on plant and sitespecific conditions and operating characteristics of each installed
radiation monitoring subsystem.
11.5.2
11.54
A COL applicant that references the U.S. EPR design certification is responsible for developing a
plantspecific process and effluent radiological sampling and analysis plan for systems not covered by
the ODCM, including provisions describing sampling and analytical frequencies, and radiological
analyses for the expected types of liquid and gaseous samples and waste media generated by the
LWMS, GWMS, and SWMS.
11.5.2
12.11
A COL applicant that references the U.S. EPR design certification will fully describe, at a functional level,
elements of the ALARA program for ensuring that occupational radiation exposures are ALARA. This
program will comply with provisions of 10 CFR Part 20 and be consistent with the guidance in RGs 1.8,
8.2, 8.7, 8.8, 8.9, 8.10, 8.13, 8.15, 8.27, 8.28, 8.29, 8.34, 8.35, 8.36, and 8.38, and the applicable portions of
NUREG1736.
12.1.3
12.21
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
for required radiation sources containing byproduct, source, and special nuclear material that may
warrant shielding design considerations. This sitespecific information will include a listing of isotope,
quantity, form, and use of all sources in this latter category that exceed 100 millicuries.
12.2.1.13
12.31
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
on the extent to which the guidance provided by RG 1.21, 1.97, 8.2, 8.8, and ANSI/ HPSN13.11999 is
employed in sampling recording and reporting airborne releases of radioactivity.
12.3.4.5
12.32
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
on estimated annual doses to construction workers in a new unit construction area as a result of
radiation from onsite radiation sources from the existing operating plant(s). This information will
include bases, models, assumptions, and input parameters associated with these annual doses.
12.3.5.1
12.33
A COL applicant that references the U.S. EPR design certification will describe the use of portable
instruments, and the associated training and procedures, to accurately determine the airborne iodine
concentration within the facility where plant personnel may be present during an accident, in
accordance with requirements of 10 CFR 50.34(f)(2)(xxvii) and the criteria in Item III.D.3.3 of
NUREG0737. The procedures for locating suspected highactivity areas will be described.
12.3.4.5
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Item No.
Description
Section
12.51
A COL applicant that references the U.S. EPR design certification will fully describe, at the functional
level, elements of the Radiation Protection Program. The purpose of the Radiation Protection Program
is to maintain occupational and public doses ALARA. The program description will identify how the
program is developed, documented, and implemented through plant procedures that address quality
requirements commensurate with the scope and extent of licensed activities. This program will comply
with the provisions of 10 CFR Parts 19, 20, 50, 52, and 71 and be consistent with the guidance in
Regulatory Guides 1.206, 1.8, 8.2, 8.4, 8.5, 8.6, 8.7, 8.8, 8.9, 8.10, 8.13, 8.15, 8.27, 8.28, 8.29, 8.34, 8.35,
8.36, 8.38, and the consolidated guidance in NUREG1736.
12.5
13.11
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
for management, technical support, and operating organizations.
13.1
13.21
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
for training programs for plant personnel.
13.2
13.31
A COL applicant that references the U.S. EPR design certification will provide a sitespecific emergency
plan in accordance with 10 CFR 50.47 and 10 CFR 50 Appendix E.
13.3
13.41
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
for operational programs and schedule for implementation.
13.4
13.51
A COL applicant that references the U.S. EPR design certification will provide sitespecific information
for administrative, operating, emergency, maintenance, and other operating procedures.
13.5
13.61
A COL applicant that references the U.S. EPR design certification will provide a sitespecific security
assessment that adequately demonstrates how the performance requirements of 10 CFR 73.55(a) are
met for the initial implementation of the security program.
13.6
13.62
A COL applicant that references the U.S. EPR design certification will provide a security plan to the NRC
to fulfill the requirements of 10 CFR 52.79(a)(35).
13.6
13.63
A COL applicant that references the U.S. EPR design certification will provide a security program
through the PSP and supporting documents such as the vital equipment list and the vital areas list that
incorporates the security features listed in the U.S. EPR FSAR Tier 2, Section 13.6.
13.6
13.64
A COL applicant that references the U.S. EPR design certification will provide a cyber security plan
consistent with 10 CFR 73.54.
13.6
13.71
A COL applicant that references the U.S. EPR design certification will submit a physical security plan to
the NRC to fulfill the fitness for duty requirements of 10 CFR Part 26.
13.7
14.21
A COL applicant that references the U.S. EPR certified design will provide site specific information that
describes the organizational units that manage, supervise, or execute any phase of the test program.
14.2.2
14.22
A COL applicant that references the U.S. EPR certified design will develop a test program that considers
the following guidance components: 1) The applicant should allow at least nine months to conduct
preoperational testing. 2) The applicant should allow at least three months to conduct startup testing,
including fuel loading, lowpower tests, and powerascension tests. 3) Plant safety will not be
dependent on the performance of untested SSCs during any phase of the startup test program.
4) Surveillance test requirements will be completed in accordance with plant Technical Specification
requirements for SSC operability before changing plant modes. 5) Overlapping test program schedules
(for multiunit sites) should not result in significant divisions of responsibilities or dilutions of the staff
provided to implement the test program. 6) The sequential schedule for individual startup tests should
establish, insofar as practicable, that test requirements should be completed prior to exceeding 25
percent power for SSC that are relied on to prevent, limit, or mitigate the consequences of postulated
accidents. 7) Approved test procedures should be in a form suitable for review by regulatory inspectors
at least 60 days prior to their intended use or at least 60 days prior to fuel loading for fuel loading and
startup test procedures. 8) Identify and cross reference each test (or portion thereof) required to be
completed before initial fuel loading and that is designed to satisfy the requirements for completing
ITAAC.
14.2.11
14.23
A COL applicant that references the US EPR design certification will provide sitespecific information for
review and approval of test procedures.
14.2.3
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Item No.
Description
Section
14.24
A COL applicant that references the US EPR design certification will address the sitespecific
administrative procedures for review and approval of test results.
14.2.5
14.25
A COL applicant that references the U.S. EPR design certification will provide sitespecific test abstract
information for the circulating water supply system.
14.2.12
14.26
A COL applicant that references the U.S. EPR certified design will either perform the natural circulation
test (Test #196) or provide justification for not performing the test. The need to perform the test will be
based on evaluation of previous natural circulation test results and a comparison of reactor coolant
system (RCS) hydraulic resistance coefficients applicable to normal flow conditions.
14.2.12
14.27
A COL applicant that references the U.S. EPR design certification will provide sitespecific test abstract
information for the cooling tower.
14.2.12
14.28
A COL applicant that references the U.S. EPR design certification will provide sitespecific test abstract
information for the raw water supply system.
14.2.12
14.29
A COL applicant that references the U.S. EPR design certification will provide sitespecific test abstract
information for personnel radiation monitors.
14.2.12
14.210
A COL applicant that references the U.S. EPR design certification will plan, and subsequently conduct,
the plant startup test program.
14.2.4
14.211
A COL applicant that references the U.S. EPR design certification will identify the specific operator
training to be conducted as part of the lowpower testing program related to the resolution of TMI
Action Plan Item I.G.1, as described in (1) NUREG0660 NRC Action Plans Developed as a Result of the
TMI2 Accident, Revision 1, August 1980, (2) NUREG0694 TMIRelated Requirements for New
Operating Licenses, June 1980, and (3) NUREG0737 Clarification of TMI Action Plan requirements.
14.2.9
14.212
A COL applicant that references the U.S. EPR design certification will provide sitespecific test abstract
information for plant laboratory equipment.
14.2.12
14.213
A COL applicant that references the U.S. EPR design certification will provide sitespecific test abstract
information for the turbine island ventilation systems.
14.3
14.31
A COL applicant that references the U.S. EPR design certification will provide ITAAC for emergency
planning, physical security, and site specific portions of the facility that are not included in the Tier 1
ITAAC associated with the certified design (10 CFR 52.80(a)).
14.3
14.32
A COL applicant that references the U.S. EPR design certification will describe the selection
methodology for sitespecific SSCs to be included in ITAAC, if the selection methodology is different
from the methodology described within the FSAR, and will also provide the selection methodology
associated with emergency planning and physical security hardware.
14.3
14.33
A COL applicant that references the U.S. EPR design certification will identify a plan for implementing
DAC. The plan will identify 1) the evaluations that will be performed for DAC, 2) the schedule for
performing these evaluations, and 3) the associated design processes and information that will be
available to the NRC for audit.
14.3
15.01
A COL applicant that references the U.S. EPR design certification will provide for staff review, prior to
the first cycle of operation, the analysis results demonstrating that the uncompensated DNBR and LPD
satisfies the SAFDL with a 95/95 assurance in accordance with ANP10287P.
15.0
16.01
Reviewer’s Notes and brackets are used to identify information or characteristics that are plant specific
or are based on preliminary design information. A COL applicant that references the U.S. EPR design
certification will provide the necessary information in response to the Reviewer’s Notes and replace
preliminary information provided in brackets of the Technical Specifications and Technical
Specification Bases with plant specific values.
16.0
17.21
A COL applicant that references the U.S. EPR design certification will provide the Quality Assurance
Programs associated with the construction and operations phases.
17.2
17.41
A COL applicant that references the U.S. EPR design certification will identify the sitespecific SSCs
within the scope of the RAP.
17.4.2
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Table 1.8-2— FSAR Sections that Address COL Items
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Item No.
Description
Section
17.42
A COL applicant that references the U.S. EPR design certification will provide the information requested
in Regulatory Guide 1.206, Section C.I.17.4.4.
17.4.4
17.61
A COL applicant that references the U.S. EPR design certification will describe the process for
determining which plant structures, systems, and components (SSC) will be included in the scope of
the Maintenance Rule Program in accordance with 10 CFR 50.65(b). The program description will
identify that additional SSC functions may be added to or subtracted from the Maintenance Rule scope
prior to fuel load, when additional information is developed (e.g., emergency operating procedures, or
EOP), and after the license is issued.
17.6.1
17.62
A COL applicant that references the U.S. EPR design certification will provide the process for
determining which SSC within the scope of the Maintenance Rule program will be tracked to
demonstrate effective control of their performance or condition in accordance with 10 CFR 50.65(a)(2).
17.6.2
17.63
A COL applicant that references the U.S. EPR design certification will provide a program description for
monitoring SSC in accordance with 10 CFR 50.65(a)(1).
17.6.2
17.64
A COL applicant that references the U.S. EPR design certification will identify and describe the program
for periodic evaluation of the Maintenance Rule program in accordance with 10 CFR 50.65(a)(3).
17.6.3
17.65
A COL applicant that references the U.S. EPR design certification will describe the program for
maintenance risk assessment and management in accordance with 10 CFR 50.65(a)(4). Since the
removal of multiple SSC from service can lead to a loss of Maintenance Rule functions, the program
description will address how removing SSC from service will be evaluated. For qualitative risk
assessments, the program description will explain how the risk assessment and management program
will preserve plantspecific key safety functions.
17.6.4
17.66
A COL applicant that references the U.S. EPR design certification will describe the program for
selection, training, and qualification of personnel with MaintenanceRulerelated responsibilities
consistent with the provisions of Section 13.2 as applicable. Training will be commensurate with
maintenance rule responsibilities, including Maintenance Rule Program administration, the expert
panel process, operations, engineering, maintenance, licensing, and plant management.
17.6.5
17.67
A COL applicant that references the U.S. EPR design certification will describe the relationship and
interface between Maintenance Rule Program and the Reliability Assurance Program.
17.6.6
17.68
A COL applicant that references the U.S. EPR design certification will describe the plan or process for
implementing the Maintenance Rule Program as described in the COL application, which includes
establishing program elements through sequence and milestones and monitoring or tracking the
performance and/or condition of SSC as they become operational. The Maintenance Rule Program will
be implemented by the time that fuel load is authorized.
17.6.8
17.69
A COL applicant that references the U.S. EPR design certification will describe the program for
Maintenance Rule implementation.
17.6
18.11
A COL applicant that references the U.S. EPR design certification will execute the NRC approved HFE
program as described in this section.
18.1
18.12
A COL applicant that references the U.S. EPR design certification will be responsible for HFE design
implementation for a new Emergency Operations Facility (EOF) and/or Operational Support Center
(OSC) and changes resulting from the addition of the U.S. EPR to an existing EOF and/or OSC.
18.1.1.3
18.51
A COL applicant that references the U.S. EPR design will confirm that actual staffing levels and
qualifications of plant personnel specified in Section 13.1 of the COL application remain bounded by
regulatory requirements and results of the staffing and qualifications analysis.
18.5
18.81
A COL applicant that references the U.S. EPR design certification will describe how HFE principles and
criteria are incorporated into the development program for site procedures.
18.8
18.91
A COL applicant that references the U.S. EPR design certification will describe how HFE principles and
criteria are incorporated into the development of training program scope, structure, and methodology.
18.9
18.121
A COL applicant that references the U.S. EPR design certification will implement a human performance
monitoring program similar to that which is described in this section.
18.12
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Table 1.8-2— FSAR Sections that Address COL Items
(Page 20 of 20)
Item No.
Description
Section
19.01
A COL applicant that references the U.S. EPR design certification will either confirm that the PRA in the
design certification bounds the site specific design information and any design changes or departures,
or update the PRA to reflect the sitespecific design information and any design changes or departures.
19.0
19.11
A COL applicant that references the U.S. EPR design certification will describe the uses of PRA in
support of licensee programs and identify and describe riskinformed applications being implemented
during the combined license application phase.
19.1.1.2
19.12
A COL applicant that references the U.S. EPR design certification will describe the uses of PRA in
support of licensee programs and identify and describe riskinformed applications being implemented
during the construction phase.
19.1.1.3
19.13
A COL applicant that references the U.S. EPR design certification will describe the uses of PRA in
support of licensee programs and identify and describe any riskinformed applications being
implemented during the operational phase.
19.1.1.4
19.14
A COL applicant that references the U.S. EPR design certification will conduct a peer review of the PRA
relative to the ASME PRA Standard prior to use of the PRA to support riskinformed applications or
before fuel load.
19.1.2.3
19.15
A COL applicant that references the U.S. EPR design certification will describe the applicant’s PRA
maintenance and upgrade program.
19.16
A COL applicant that references the U.S. EPR design certification will confirm that the designspecific
U.S. EPR PRAbased seismic margins assessment is bounding for their specific site.
19.17
A COL applicant that references the U.S. EPR design certification will perform the sitespecific screening
analysis and the sitespecific risk analysis for external events applicable to their site, including a
sitespecific PRAbased SMA for soil effects (including sliding and overturning, liquefaction, and slope
failure).
19.1.5.4
19.18
A COL applicant that references the U.S. EPR design certification will describe the uses of PRA in
support of sitespecific design programs and processes during the design phase.
19.1.1.1
19.19
A COL applicant that references the U.S. EPR design certification will review asdesigned and asbuilt
information and conduct walkdowns as necessary to confirm that the assumptions used in the PRA
(including PRA inputs to RAP and SAMDA) remain valid with respect to internal events, internal flood
and fire events (routings and locations of pipe, cable and conduit), and HRA analyses (development of
operating procedures, emergency operating procedures and severe accident management guidelines
and training), external events including PRAbased seismic margins HCLPF fragilities, and LPSD
procedures.
19.1.2.2
19.21
A COL applicant that references the U.S. EPR design certification will develop and implement severe
accident management guidelines prior to fuel loading using the Operating Strategies for Severe
Accidents (OSSA) methodology described in U.S. EPR FSAR Section 19.2.5.
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19.1.2.4.1
19.1.5.1.2.4
19.2.5
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FSAR: Chapter 1.0
1.9
Conformance with Regulatory Criteria
CONFORMANCE WITH REGULATORY CRITERIA
This section of the U.S. EPR FSAR is incorporated by reference with the following supplements.
The U.S. EPR FSAR includes the following COL Item in Section 1.9:
A COL applicant that references the U.S. EPR design certification will review and
address the conformance with regulatory criteria in effect six months before the
docket date of the COL application for the sitespecific portions and operational
aspects of the facility design.
This COL Item is addressed as follows:
A guide to U.S. EPR conformance with regulatory criteria is presented in Section 1.9 of the U.S.
EPR FSAR. Conformance with regulatory criteria was summarized in Sections 1.9.1 through
1.9.5 of the U.S. EPR FSAR, including four conformance demonstration tables. These four
conformance demonstration tables include U.S. EPR FSAR Table 1.9–2, U.S. EPR Conformance
with Regulatory Guides, U.S. EPR FSAR Table 1.9–3, U.S. EPR Conformance with TMI
Requirements (10 CFR 50.34(f)) and Generic Issues (NUREG0933), U.S. EPR FSAR Table 1.9–4,
U.S. EPR Conformance with Advanced and Evolutionary LightWater Reactor Design Issues
(SECY93087), Table 1–2, U.S. EPR Conformance with Standard Review Plan (NUREG0800)
from ANP10292, U.S. EPR Conformance with Standard Review Plan (NUREG0800) Technical
Report (AREVA 2009).
Codes used to indicate conformance determinations in the ”U.S. EPR Assessment” columns of
the four conformance demonstration tables are listed in Table 1.91 of the U.S. EPR FSAR. The
definition of the conformance code ”N/ACOL” is:
Guidance addresses concerns not addressed with the context of a design
certification application and must be addressed by a combined license (COL)
applicant referencing the U.S. EPR design certification.
Sitespecific conformance to relevant aspects of the associated NRC guidance, as stipulated
within the specific context of the cited guidance statement, was assessed for the regulatory
guidance assigned a code of ”N/ACOL” in the four conformance demonstration tables of the
U.S. EPR FSAR.
Regulatory guidance not applicable to {CCNPP Unit 3} or not within the scope of the FSAR is
not identified as nonconforming. Therefore, exceptions to this nonapplicable regulatory
guidance are not required. For example, Regulatory Guide 1.81, Shared Emergency and
Shutdown Electric Systems for MultiUnit Nuclear Power Plants, is not applicable to {CCNPP
Unit 3} since it does not share emergency or shutdown electric systems with {CCNPP Units 1
and 2}. The results of these assessments are presented in Sections 1.9.1, 1.9.2, 1.9.3, and 1.9.5.
Conformance with regulatory criteria associated with operational experience (generic
communications) is addressed in Section 1.9.4.
1.9.1
Conformance with Regulatory Guides
Sitespecific assessment of conformance with the regulatory guidance identified with a code
of ”N/ACOL” in Table 1.92 of the U.S. EPR FSAR was performed. Those Regulatory Guides for
which the facility takes exception are identified in Table 1.9-1. The document and section that
address the exceptions are also provided in Table 1.9-1. No exceptions are taken to other
applicable Regulatory Guides included in U.S. EPR FSAR Table 1.92.
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FSAR: Chapter 1.0
1.9.2
Conformance with Regulatory Criteria
Conformance with the Standard Review Plan
Sitespecific assessment of conformance with regulatory guidance identified with a code
of ”N/ACOL” in Table 12 of ANP10292 (AREVA, 2009) was performed. No exceptions are
taken to the applicable NUREG0800 acceptance criteria included in ANP10292, Table 12.
1.9.3
Generic Issues
Assessment of the conformance with regulatory requirements and guidance identified with a
code of ”N/ACOL” in Table 1.93 of the U.S. EPR FSAR was performed. {CCNPP Unit 3}
conforms to the regulatory requirements and applicable regulatory guidance in effect six
months prior to the submittal date of the COL application that were assigned an assessment
code of ”N/ACOL” in Table 1.93 of the U.S. EPR FSAR.
1.9.4
Operational Experience (Generic Communications)
Operational experience described in Bulletins and Generic Letters are incorporated by the NRC
staff into updates of applicable sections of NUREG0800. The U.S. EPR design certification
application was submitted May29, 2009 (AREVA, 2009) and addressed conformance with the
most recent NUREG0800 updates relative to the U.S. EPR design certification application,
March 2007 (for NUREG0800 Chapters 118) and June 2007 (for NUREG0800 Chapter 19). {In
the time period from the mentioned NUREG0800 updates to September, 2007 (i.e. six months
prior to submittal of the remainder of the CCNPP Unit 3 COL application), no new applicable
NRC Bulletins or Generic Letters were issued. Therefore, the conformance assessment for
CCNPP Unit 3 relative to operational experience is satisfied by the conformance assessment
provided in Section 1.9.2 above.}
1.9.5
Advanced and Evolutionary Light-Water Reactor Design Issues
Assessment of the conformance with regulatory guidance identified with a code of ”N/ACOL”
in Table 1.94 of the U.S. EPR FSAR was performed. {CCNPP Unit 3} conforms to the applicable
regulatory guidelines in effect six months prior to the submittal date of the COL application
that were assigned an assessment code of ”N/ACOL” in Table 1.94 of the U.S. EPR FSAR.
1.9.6
References
{AREVA, 2009. U.S. EPR Conformance with Standard Review Plan (NUREG0800) Technical
Report, ANP10292, Revision 1, AREVA, May 2009.}
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FSAR: Chapter 1.0
Conformance with Regulatory Criteria
Table 1.9-1— {Conformance with Regulatory Guides}
(Page 1 of 3)
RG / Rev Description
Exception Descriptions
Reference
Division 1 Regulatory Guides
FSAR 13.1.3.1
Licensed personnel are not able to meet Regulatory Guide 1.8,
FSAR 13.2
Rev. 3 operating plant experience requirements on CCNPP Unit
Technical
3. Regulatory Guide 1.8, Rev. 2, Regulatory Position C.1.b will be
Specifications
followed instead for a cold licensing program.
5.3.1
1.8, R3
Qualification and Training of
Personnel for Nuclear Power plants
Quality Control and Quality Assurance personnel will meet
education and experience requirements in accordance with the FSAR 13.1.3.1
approved Quality Assurance Program Description.
The Quality Assurance Manager will approve the use of an
alternative for the formal education and experience
requirements for Quality Assurance positions in accordance
with the approved Quality Assurance Program Description.
FSAR 13.1.3.1
1.16, R4
The annual operating report and monthly operating report are
submitted in accordance with Technical Specifications. Event
Reporting of Operating Information
reporting is performed in accordance with 10 CFR 50.72 and
—Appendix A Technical
50.73 utilizing the guidance of NUREG1022. Technical
Specifications
Specifications reporting requirements are implemented, as
required.
License
Condition
and Technical
Specifications
1.23, R1
Meteorological Monitoring
Programs for Nuclear Power Plants
Atmospheric moisture data for the UHS and CWS cooling
towers are not taken on site. They are taken from the closest
source of atmospheric moisture data at the Patuxent River
Naval Air Station.
The meteorological tower is at a different elevation than plant
grade to assure the tower is on a level, open terrain.
No wind shield installed on the precipitation gauge prior to
June 2009.
A digital data sampling rate of 10 seconds will be used instead
of 5 seconds.
FSAR
2.3.3.1.7,
2.3.1.2.2.13,
and 2.3.3.2.7
ER 6.4.1,
6.4.1.7, and
6.4.2.7
1.28, R3
Quality Assurance Program
Requirements
Quality Assurance Program Requirements are in accordance
with the approved Quality Assurance Program Description.
FSAR 17.5
1.30, R0
Quality Assurance Requirements for
the Installation, Inspection, and
Testing of Instrumentation and
Electric Equipment
Quality Assurance requirements for the installation, inspection,
and testing of instrumentation and electric equipment are in
accordance with the approved Quality Assurance Program
Description.
FSAR 17.5
1.33, R2
Quality Assurance Program
Requirements (Operation)
Quality Assurance Program Requirements for Operation are in
accordance with the approved Quality Assurance Program
Description.
FSAR 17.5
1.38, R2
Quality Assurance Requirements for
Quality Assurance requirements for packaging, shipping,
Packaging, Shipping, Receiving,
receiving, storage, and handling of items are in accordance
Storage, Handling of Items for
with the approved Quality Assurance Program Description.
WaterCooled Nuclear Power Plants
FSAR 17.5
1.39, R2
Housekeeping Requirements for
Watercooled Nuclear Power Plants
Quality Assurance requirements for housekeeping are in
accordance with the approved Quality Assurance Program
Description.
FSAR 17.5
1.70, R3
Standard Format and Content of
Safety Analysis Reports for Nuclear
Power Plants (LWR Edition)
The format and content of the FSAR follows Regulatory Guide
1.206 and the U.S. EPR FSAR.
FSAR 1.1.6
CCNPP Unit 3
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© 2007-2010 UniStar Nuclear Services, LLC. All rights reserved.
COPYRIGHT PROTECTED
Rev. 7
FSAR: Chapter 1.0
Conformance with Regulatory Criteria
Table 1.9-1— {Conformance with Regulatory Guides}
(Page 2 of 3)
RG / Rev Description
Exception Descriptions
Reference
Quality Assurance Program Requirements for installation,
inspection and testing of structural concrete and structural
steel during the construction phase of nuclear power plants are
in accordance with the approved Quality Assurance Program
Description.
FSAR 17.5
Quality Assurance Program Requirements for installation,
inspection, and testing of mechanical equipment and systems
are in accordance with the approved Quality Assurance
Program Description.
FSAR 17.5
Soil boring quantities, locations, and depths, vertical deviation
measurements, and soil core photography deviate from
Regulatory Guide 1.132.
FSAR
2.5.4.2.2.2
Laboratory Investigations of Soils
1.138, R2 and rocks for Engineering Analysis
and Design of Nuclear Power Plants
More recent ASTM or EPA standards were used that are
equivalent to the outofdate and uncommon test procedures
discussed in Regulatory Guide 1.138, R2
FSAR 2.5.4.2.4
Procedures and Criteria for
1.198, R0 Assessing Seismic Soil Liquefaction
at Nuclear Power Plant Sites
Aerial photography was not conducted to plan and conduct
the subsurface investigation due to uniformity in geologic
conditions between the existing CCNPP Units 1 and 2 and
CCNPP Unit 3.
FSAR 2.5.4.8.2
EPRI Report TR1014381 was used in lieu of EPRI Report
1013105. The former report is the final EPRI report versus the
latter update report cited in the Regulatory Guide. There is no
technical difference between the recommended CEUS sigma
values and report conclusions.
Equation 7 in Appendix D, Step 3, Determining Controlling
Earthquakes, was not used because it is incorrect. A corrected
equation was used instead.
FSAR 2.5.2.4.5
The mean magnitude and mean distance contributing to high
frequency ground motion was used versus the average
magnitude and average distance specified in Appendix D. Use
of the mean provides a more accurate description of the
magnitudes and distances.
FSAR 2.5.2.4.6
1.94, R1
Quality Assurance Requirements for
Installation, Inspection and Testing
of Structural Concrete and
Structural Steel During the
Construction Phase of Nuclear
Power Plants
Quality Assurance Requirements for
Installation, Inspection, and Testing
1.116, R0
of Mechanical Equipment and
Systems
1.132, R2
Site Investigation for Foundations
of Nuclear Power Plants
A PerformanceBased Approach to
1.208, R0 Define the SiteSpecific Earthquake
Ground Motion
Division 4 Regulatory Guides
4.4, R0
Reporting Procedure for
Mathematical Models Selected to
Predict Heated Effluent Dispersion
in Nuclear Water Bodies
NUREG1555 Section 5.3.2 was utilized.
ER 5.3.2
Division 5 Regulatory Guides
None
Division 8 Regulatory Guides
8.2, R0
Guide for Administrative Practices
in Radiation Monitoring
CCNPP Unit 3
The reference to 10 CFR 20.401 is no longer valid in the current
version of 10 CFR Part 20 ANSI N13.21969 was reaffirmed in
1988.
1-55
© 2007-2010 UniStar Nuclear Services, LLC. All rights reserved.
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FSAR 12.5
Rev. 7
FSAR: Chapter 1.0
Conformance with Regulatory Criteria
Table 1.9-1— {Conformance with Regulatory Guides}
(Page 3 of 3)
RG / Rev Description
Exception Descriptions
Reference
8.4, R0
The reference to 10 CFR 20.202 (a) and 20.401 is no longer valid
in the current version of 10 CFR Part 20.
ANSI N13.51972 was reaffirmed in 1989.
The two performance criteria specified in Regulatory Guide 8.4
DirectReading and
(accuracy and leakage) for these devices are met using
IndirectReading Pocket Dosimeters
acceptance standards in ANSI N3221997 ”American National
Standard Inspection, Test, Construction, and Performance
Requirements for Direct Reading Electrostatic/ Electroscope
Type Dosimeters.”
FSAR 12.5
8.6, R0
Standard Test Procedure for
GeigerMuller Counters
The instrument calibration program is based upon criteria in
ANSI N3231978 (R1993) ”Radiation Protection Instrumentation
and Calibration.”
FSAR 12.5
8.8, R3
Information Relevant to Ensuring
That Occupational Radiation
Exposures at Nuclear Power
Stations Will Be As Low As
Reasonably Achievable
Section C.3.b – Regulatory Guide 1.16 Section C.1.b (3) data is
no longer reported. Reporting is also no longer required for
Section C.1.b (2).
Sections C.4.b – C.4.d – Conformance is with the latest revision
of NUREG0041.
FSAR 12.5
CCNPP Unit 3
1-56
© 2007-2010 UniStar Nuclear Services, LLC. All rights reserved.
COPYRIGHT PROTECTED
Rev. 7